Nuclear Energy Publications
This comprehensive collection of publications issued by the Department of Nuclear Energy gives you access to over 2 000 TECDOCs, conference proceedings, technical reports, and other nuclear energy-related publications. Where available, publications can be downloaded in PDF and/or ordered from the IAEA's Publications Section.
You can browse through all publications listed below, or find individual documents in your area of interest using the search function on the left-side menu.
IAEA-RDS-1/05
ISBN: 92-0-159385-6
Publication Date: 24-9-1985
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/06
ISBN: 92-0-159386-4
Publication Date: 13-8-1986
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/07
ISBN: 92-0-159287-6
Publication Date: 18-8-1987
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/08
ISBN: 92-0-159288-4
Publication Date: 25-7-1988
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/09
ISBN: 92-0-159289-2
Publication Date: 2-8-1989
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/10
ISBN: 92-0-159190-X
Publication Date: 24-8-1990
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-2/05
ISBN: 92-0-159185-3
Publication Date: 31-5-1985
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/06
ISBN: 92-0-159186-1
Publication Date: 30-4-1986
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/07
ISBN: 92-0-159087-3
Publication Date: 29-4-1987
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/08
ISBN: 92-0-159188-8
Publication Date: 2-5-1988
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/09
ISBN: 92-0-159089-X
Publication Date: 17-5-1989
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/10
ISBN: 92-0-159090-3
Publication Date: 18-5-1990
Subject Classification: 0700 - Nuclear power
IAEA-TCS-01
Publication Date: 21-6-1990
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-322
Publication Date: 18-1-1985
IAEA-TECDOC-327
Publication Date: 14-2-1985
IAEA-TECDOC-328
Publication Date: 19-3-1985
IAEA-TECDOC-329
Publication Date: 4-4-1985
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-332
Publication Date: 4-4-1985
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-333
Publication Date: 3-4-1985
IAEA-TECDOC-334
Publication Date: 31-5-1985
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-337
Publication Date: 12-7-1985
IAEA-TECDOC-341
Publication Date: 19-7-1985
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
IAEA-TECDOC-343
Publication Date: 8-7-1985
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-344
Publication Date: 7-10-1985
IAEA-TECDOC-347
Publication Date: 15-8-1985
IAEA-TECDOC-348
Publication Date: 7-11-1985
Subject Classification: 0603 - Nuclear power plants; 0604 - Research reactors
IAEA-TECDOC-352
Publication Date: 12-11-1985
IAEA-TECDOC-354
Publication Date: 27-1-1988
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-354
Publication Date: 22-2-1988
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-354
Publication Date: 10-11-1986
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-354
Publication Date: 4-10-1985
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-355
Publication Date: 6-11-1985
Subject Classification: 0610 - Accident response
IAEA-TECDOC-356
Publication Date: 19-11-1985
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-358
Publication Date: 17-12-1985
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-359
Publication Date: 21-11-1985
Subject Classification: 0611 - Radioactive waste management; 0614 - Legal and governmental aspects
IAEA-TECDOC-360
Publication Date: 22-11-1985
Subject Classification: 0602 - Fuel fabrication and storage; 0611 - Radioactive waste management
IAEA-TECDOC-361
Publication Date: 28-1-1986
IAEA-TECDOC-362
Publication Date: 16-1-1986
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-364
Publication Date: 10-3-1986
IAEA-TECDOC-366
Publication Date: 6-3-1986
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-367
Publication Date: 3-4-1986
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-370
Publication Date: 4-4-1986
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-374
Publication Date: 24-6-1986
Subject Classification: 0606 - Transport of radioactive material; 0609 - Radiation protection
IAEA-TECDOC-375
Publication Date: 19-6-1986
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-376
Publication Date: 6-6-1986
IAEA-TECDOC-377
Publication Date: 6-6-1986
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-378
Publication Date: 28-8-1986
IAEA-TECDOC-379
Publication Date: 18-6-1986
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-383
Publication Date: 21-8-1986
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-386
Publication Date: 30-9-1986
IAEA-TECDOC-387
Publication Date: 14-11-1986
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-388
Publication Date: 17-10-1986
Subject Classification: 0607 - Fusion reactors
IAEA-TECDOC-389
Publication Date: 6-10-1986
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-390
Publication Date: 3-10-1986
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-393
Publication Date: 11-12-1986
IAEA-TECDOC-397
Publication Date: 16-12-1986
IAEA-TECDOC-398
Publication Date: 19-12-1986
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-399
Publication Date: 19-12-1986
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-400
Publication Date: 22-1-1987
Subject Classification: 0604 - Research reactors; 0612 - Safety analysis
IAEA-TECDOC-401
Publication Date: 5-2-1987
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-402
Publication Date: 25-2-1987
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-403
Publication Date: 20-2-1987
Subject Classification: 0604 - Research reactors
IAEA-TECDOC-408
Publication Date: 25-2-1987
IAEA-TECDOC-412
Publication Date: 20-3-1987
IAEA-TECDOC-413
Publication Date: 11-5-1987
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-414
Publication Date: 28-4-1987
IAEA-TECDOC-415
Publication Date: 8-4-1987
Manual on Quality Assurance for the Survey, Evaluation and Confirmation of Nuclear Power Plant Sites
IAEA-TECDOC-416
Publication Date: 11-5-1987
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-418
Publication Date: 11-5-1987
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-419
Publication Date: 5-6-1987
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-420
Publication Date: 18-6-1987
IAEA-TECDOC-421
Publication Date: 13-7-1987
IAEA-TECDOC-423
Publication Date: 23-6-1987
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-424
Publication Date: 23-6-1987
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-425
Publication Date: 13-7-1987
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-427
Publication Date: 14-10-1987
IAEA-TECDOC-429
Publication Date: 21-9-1987
IAEA-TECDOC-430
Publication Date: 25-9-1987
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-431
Publication Date: 10-9-1987
IAEA-TECDOC-433
Publication Date: 4-11-1987
IAEA-TECDOC-434
Publication Date: 4-11-1987
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-436
Publication Date: 24-11-1987
IAEA-TECDOC-439
Publication Date: 23-12-1987
IAEA-TECDOC-440
Publication Date: 12-1-1988
Subject Classification: 0607 - Fusion reactors
IAEA-TECDOC-442
Publication Date: 27-11-1987
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-443
Publication Date: 23-12-1987
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
IAEA-TECDOC-444
Publication Date: 11-12-1987
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-446
Publication Date: 23-12-1987
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-447
Publication Date: 3-2-1988
This fourth updated Radioactive Waste Management Glossary is intended to provide a source of terms that are commonly used or have special meanings in the field of radioactive waste management. The glossary includes new terms that have come into use in the past decade and terms whose meanings have changed. The terms that are included have all become part of accepted international usage.
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-449
Publication Date: 25-2-1988
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-450
Publication Date: 14-4-1988
Subject Classification: 0603 - Nuclear power plants; 0609 - Radiation protection
IAEA-TECDOC-451
Publication Date: 6-4-1988
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-453
Publication Date: 5-5-1988
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-458
Publication Date: 12-4-1988
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-460
Publication Date: 21-6-1988
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-461
Publication Date: 30-5-1988
IAEA-TECDOC-463
Publication Date: 17-6-1988
IAEA-TECDOC-466
Publication Date: 12-7-1988
IAEA-TECDOC-468
Publication Date: 14-7-1988
IAEA-TECDOC-470
Publication Date: 12-9-1988
IAEA-TECDOC-471
Publication Date: 15-10-1988
IAEA-TECDOC-472
Publication Date: 27-9-1988
IAEA-TECDOC-473
Publication Date: 16-8-1988
Subject Classification: 0610 - Accident response
IAEA-TECDOC-474
Publication Date: 24-10-1988
IAEA-TECDOC-477
Publication Date: 2-11-1988
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-478
Publication Date: 7-11-1988
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-479
Publication Date: 20-10-1988
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-480
Publication Date: 20-12-1988
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-482
Publication Date: 19-10-1988
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-484
Publication Date: 19-12-1988
IAEA-TECDOC-485
Publication Date: 1-11-1988
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-487
Publication Date: 24-1-1989
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-489
Publication Date: 11-1-1989
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-492
Publication Date: 1-3-1989
Subject Classification: 0601 - Uranium mining and milling; 0611 - Radioactive waste management
IAEA-TECDOC-495
Publication Date: 28-3-1989
IAEA-TECDOC-497
Publication Date: 22-3-1989
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-498
Publication Date: 21-4-1989
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-499
Publication Date: 10-4-1989
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-500
Publication Date: 21-4-1989
IAEA-TECDOC-503
Publication Date: 12-4-1989
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-504
Publication Date: 25-4-1989
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-505
Publication Date: 20-4-1989
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-507
Publication Date: 3-7-1989
IAEA-TECDOC-508
Publication Date: 14-7-1989
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-510
Publication Date: 30-8-1989
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-511
Publication Date: 19-6-1989
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-513
Publication Date: 25-9-1989
IAEA-TECDOC-514
Publication Date: 25-7-1989
IAEA-TECDOC-516
Publication Date: 11-8-1989
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-517
Publication Date: 30-8-1989
Subject Classification: 0604 - Research reactors; 0612 - Safety analysis
IAEA-TECDOC-521
Publication Date: 25-9-1989
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management
IAEA-TECDOC-522
Publication Date: 19-10-1989
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-523
Publication Date: 2-10-1989
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-524
Publication Date: 5-10-1989
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-525
Publication Date: 6-12-1989
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-526
Publication Date: 23-11-1989
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-528
Publication Date: 23-11-1989
IAEA-TECDOC-529
Publication Date: 17-5-1990
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-533
Publication Date: 2-1-1990
IAEA-TECDOC-535
Publication Date: 8-3-1990
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-538
Publication Date: 8-2-1990
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-540
Publication Date: 29-1-1990
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-541
Publication Date: 14-2-1990
IAEA-TECDOC-542
Publication Date: 21-2-1990
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-543
Publication Date: 1-2-1990
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-546
Publication Date: 22-2-1990
Subject Classification: 0603 - Nuclear power plants; 0802 - Fuel fabrication and performance; 0802 - Fuel fabrication and performance
IAEA-TECDOC-547
Publication Date: 20-3-1990
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-548
Publication Date: 15-3-1990
Subject Classification: 0605 - Radiation sources and accelerators; 0611 - Radioactive waste management
IAEA-TECDOC-549
Publication Date: 17-5-1990
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-550
Publication Date: 4-5-1990
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-552
Publication Date: 10-4-1990
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-553
Publication Date: 9-8-1990
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-555
Publication Date: 8-6-1990
IAEA-TECDOC-556
Publication Date: 8-6-1990
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-557
Publication Date: 16-5-1990
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-559
Publication Date: 21-9-1990
Subject Classification: 0603 - Nuclear power plants; 0608 - Waste repositories
IAEA-TECDOC-560
Publication Date: 30-5-1990
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-561
Publication Date: 21-9-1990
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-562
Publication Date: 30-5-1990
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-563
Publication Date: 21-8-1990
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
IAEA-TECDOC-565
Publication Date: 19-10-1990
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-566
Publication Date: 8-10-1990
Subject Classification: 0609 - Radiation protection; 0612 - Safety analysis
IAEA-TECDOC-567
Publication Date: 13-11-1990
IAEA-TECDOC-568
Publication Date: 12-10-1990
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-569
Publication Date: 4-10-1990
IAEA-TECDOC-570
Publication Date: 10-9-1990
IAEA-TECDOC-573
Publication Date: 29-10-1990
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-574
Publication Date: 18-9-1990
Subject Classification: 0701 - Nuclear power planning and economics; 0703 - Reactor technology
IAEA-TECDOC-577
Publication Date: 15-11-1990
IAEA-TECDOC-579
Publication Date: 11-12-1990
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
IAEA-TECDOC-580
Publication Date: 21-12-1990
Subject Classification: 0611 - Radioactive waste management; 0803 - Spent fuel management
IAEA/WMRA/18
Publication Date: 9-3-1988
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0800 - Nuclear fuel cycle and waste management; 0803 - Spent fuel management; 0804 - Waste management
IAEA/WMRA/19
Publication Date: 21-6-1989
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0800 - Nuclear fuel cycle and waste management; 0803 - Spent fuel management; 0804 - Waste management
IAEA/WMRA/20
Publication Date: 8-11-1990
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0800 - Nuclear fuel cycle and waste management; 0803 - Spent fuel management; 0804 - Waste management
STI/DOC/010/245
ISBN: 92-0-155085-5
Publication Date: 9-4-1985
Subject Classification: 0701 - Nuclear power planning and economics
STI/DOC/010/246
ISBN: 92-0-155185-1
Publication Date: 29-5-1985
Subject Classification: 0703 - Reactor technology
STI/DOC/010/247
ISBN: 92-0-125085-1
Publication Date: 22-7-1985
Subject Classification: 0612 - Safety analysis; 1300 - Environment
STI/DOC/010/249
ISBN: 92-0-125185-8
Publication Date: 10-9-1985
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/250
ISBN: 92-0-125285-4
Publication Date: 4-9-1985
Subject Classification: 0612 - Safety analysis; 1300 - Environment
STI/DOC/010/251
ISBN: 92-0-125385-0
Publication Date: 2-9-1985
Subject Classification: 0608 - Waste repositories
STI/DOC/010/252
ISBN: 92-0-125485-7
Publication Date: 25-10-1985
Subject Classification: 0300 - Nuclear Measurements, Techniques and Instrumentation; 0609 - Radiation protection
STI/DOC/010/253
ISBN: 92-0-125585-3
Publication Date: 7-10-1985
Subject Classification: 0608 - Waste repositories; 0804 - Waste management
STI/DOC/010/254
ISBN: 92-0-125685-X
Publication Date: 7-11-1985
Subject Classification: 0804 - Waste management
STI/DOC/010/255
ISBN: 92-0-145085-0
Publication Date: 7-11-1985
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/DOC/010/256
ISBN: 92-0-125785-6
Publication Date: 6-11-1985
Subject Classification: 0608 - Waste repositories
STI/DOC/010/257
ISBN: 92-0-125885-2
Publication Date: 7-11-1985
Subject Classification: 0804 - Waste management
STI/DOC/010/258
ISBN: 92-0-125985-9
Publication Date: 12-12-1985
Subject Classification: 0804 - Waste management
STI/DOC/010/259
ISBN: 92-0-145086-6
Publication Date: 25-4-1986
Borehole logging is a basic tool in the exploration for and delineation of uranium deposits. The radioactivity associated with the uranium can be used for the quantitative evaluation of the uranium content of rocks intercepted by the borehole. This manual is designed to provide an explanation of such procedures in a clear and straightforward manner so as to meet the needs of field practitioners. Contents: Introduction; The borehole: Its characteristics and effects; Gross count gamma ray logging; Resistance, resistivity and conductivity; Spontaneous potential; Density logging; Neutron logging; Field procedures; Logging examples; Appendix 1: Calibration procedure for gross count gamma ray logging; Appendix 2: Correlation factors for gross count gamma ray logging; Appendix 3: Glossary and reference data.
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/DOC/010/260
ISBN: 92-0-125086-X
Publication Date: 6-5-1986
Subject Classification: 0303 - Dosimetry (techniques); 0609 - Radiation protection
STI/DOC/010/262
ISBN: 92-0-155086-3
Publication Date: 23-6-1986
Subject Classification: 0603 - Nuclear power plants; 0704 - Quality assurance; 0705 - Qualification and training of personnel
STI/DOC/010/263
ISBN: 92-0-125186-6
Publication Date: 4-7-1986
This document was originally approved by GESAMP (the IMO/FAO/UNESCO/WMO/WHO/IAEA/UN/UNEP Joint Group of Experts on the Scientific Aspects of Marine Pollution) in March 1983 at its thirteenth session for publication as GESAMP Reports and Studies No. 19. Recognizing that its usefulness is far broader than its application to calculations of concentrations of radioactive materials in the deep sea, the IAEA has undertaken to republish the report in its Technical Reports Series with the concurrence of the other technical bodies of GESAMP. Contents: Introduction; General requirements for ocean models for contaminant transport; Oceanographic processes relevant to deep-sea contaminant transport; Survey of existing and potential models; Recommended models; Future research needs; Appendix I: Geochemical properties and observations of the deep ocean; Appendix II: Natural history of the ocean; Appendix III: Quantitative estimates of various biological processes; Appendix IV: A simple finite ocean diffusive model; Appendix V: Parametrization of boundary scavenging processes; Appendix VI: Vertical, one-dimensional, one- and two-layer boundary scavenging models; Appendix VII: The effects of strong local scavenging; Appendix VIII. A two-dimensional ocean dispersion model; Appendix IX. A hybrid vertical scavenging model; Appendix X. Estimation of concentra-tions in food chains; References; Glossary; List of basic symbols used.
Subject Classification: 0611 - Radioactive waste management; 0612 - Safety analysis
STI/DOC/010/265
ISBN: 92-0-155186-X
Publication Date: 20-8-1986
The final report of an IAEA co-ordinated research programme involving nine organizations in eight Member States during the period 19771983. The irradiation response of seven steels typical of modern practice, in the form of plants, forgings and submerged arc welds supplied by worldwide suppliers, was determined under light water reactor pressure vessel irradiation conditions. Contents: Introduction; Scientific scope and programme goals; Standard part of phase 2 programme; Irradiation conditions; Experimental results; Discussion of results; Conclusions; Appendix A: List of participants in the programme; Appendix B: Materials specification and identification; Appendix C: Expressions used to define errors in linear regression analyses; Appendix D: Summary of experimental data; List of symbols and abbreviations.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/DOC/010/266
ISBN: 92-0-155286-6
Publication Date: 26-8-1986
The guidebook provides recommendations, based on the experience of both developed and developing countries, for upgrading or establishing national education and training capabilities in engineering and science in order to develop qualified personnel for nuclear power programmes. Special consideration has been given to the specific needs and conditions of developing countries. Contents: Introduction; 1. Important aspects of engineering and science education for nuclear power; 2. Nuclear-oriented programmes in mechanical, electrical, chemical, nuclear, electronics engineering and in radiation health physics; 3. Nuclear specialization (S) programmes; 4. Undergraduate (U) and post-graduate (P) programmes in nuclear-oriented mechanical (U1, P1), electrical (U2, P2) and chemical (U3, P3) engineering and postgraduate programme in nuclear engineering (P4) for graduates of nuclear-oriented mechanical and electrical undergraduate programmes; 5. Integrated undergraduate (U) and postgraduate (P) programmes in nuclear engineering (U5, P5) and radiation health physics (U6, P6); 6. Basic nuclear science and engineering laboratory; 7. Measures for implementing and improving engineering and science education and training capabilities for nuclear power personnel.
Subject Classification: 0603 - Nuclear power plants; 0705 - Qualification and training of personnel
STI/DOC/010/267
ISBN: 92-0-125286-2
Publication Date: 19-9-1986
This report is a review of the current state of the methodology and technology of decommissioning nuclear facilities including remote systems technology. Contents: Introduction; Scope; Definitions of the basic stages of decommissioning; Consideration affecting decommissioning choices; Methodology and technology of decommissioning; Decommissioning safety; Facilitation of decommissioning; Information database; Conclusions and recommendations: Annex A: Inventory of nuclear facilities of interest to decommissioning; Annex B: Disassembly techniques; Annex C: Remotely controlled equipment for decommissioning.
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/268
ISBN: 92-0-125386-9
Publication Date: 12-12-1986
This users manual provides Member States implementing the IAEA Codes and Safety Guides (NUSS) with practical examples of management organization, good practices, methods and techniques for the maintenance of systems and components important to safety. It contains a detailed description of management systems, administrative controls and procedures for maintenance activities and some aspects of surveillance and verification activities. Contents: Introduction; Scope; Maintenance programme; Implementation of maintenance programme; Surveillance and verification activities; Annex I. Examples of documents; Annex II. Descriptions of practices.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/DOC/010/269
ISBN: 92-0-155386-2
Publication Date: 16-12-1986
Subject Classification: 0701 - Nuclear power planning and economics
STI/DOC/010/270
ISBN: 92-0-145286-1
Publication Date: 19-12-1986
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/DOC/010/270/M
ISBN: 92-0-145386-8
Publication Date: 19-12-1986
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/DOC/010/271
ISBN: 92-0-155087-1
Publication Date: 9-2-1987
Subject Classification: 0701 - Nuclear power planning and economics
STI/DOC/010/272
ISBN: 92-0-125087-8
Publication Date: 24-4-1987
Subject Classification: 0804 - Waste management
STI/DOC/010/274
ISBN: 92-0-125187-4
Publication Date: 15-5-1987
This report is aimed at: (a) quantifying airborne radionuclides in off-gas and ventilation air streams in nuclear power plants; (b) reviewing the current status and latest development trends in design for normal operation and design basis accidents; (c) providing guidelines for design. Contents: Introduction; General design principles; LWR nuclear power plants; Other types of reactors; Trends in off-gas and air cleaning system design; References; Appendix A.I: Source term specifications for LWRs; Appendix A.II: Examples of calculations using the GALE code.
Subject Classification: 0603 - Nuclear power plants; 0804 - Waste management
STI/DOC/010/275
ISBN: 92-0-155187-8
Publication Date: 29-5-1987
This Guidebook constitutes a complement to a series of technical guidebooks: Technical Evaluation of Bids for Nuclear Power Plants, Technical Reports Series No. 204 (1981); Guidebook on the Introduction of Nuclear Power, Technical Reports Series No. 217 (1982); and Economic Evaluation of Bids for Nuclear Power Plants, 1999 Edition, Technical Reports Series No. 369 (2000). These provide, in particular, information on the process of plant acquisition and advice on the principal activities involved in the planning and implementation of nuclear power projects, as well as on the infrastructure requirements and development needs for the successful implementation of a nuclear power programme. These reports are directed to the special needs of developing countries. Contents: Introduction; Part 1. Information provided by the owner; Part 2. Information requested from the bidders; Appendix A. IAEA Account System for Nuclear Power Plants; Appendix B. Technical questionnaires; Appendix C. Abbreviations; Bibliography.
Subject Classification: 0701 - Nuclear power planning and economics
STI/DOC/010/276
ISBN: 92-0-125287-0
Publication Date: 21-8-1987
The evaluation of optimum waste management practices for the long lived iodine-129 has received special consideration with the expansion of nuclear power programmes. Radioiodine can be removed from off-gas streams by a variety of physical, chemical or physicochemical processes. This publication reviews the various techniques collectively and reports on current developments of the techniques used in the immobilization of recovered iodine and disposal of the conditioned wastes, with due regard to the radiological hazards involved. Contents: 1. Introduction; 2. Characteristics and arisings of iodine-129; 3. Monitoring iodine-129; 4. Treatment and conditioning of iodine-129 in nuclear fuel reprocessing; 5. Disposal options and associated radiological impacts; 6. Radiological significance of iodine-129 in disposal of unreprocessed spent fuel; 7. Cost of iodine-129 management; 8. Conclusions and recommendations.
Subject Classification: 0804 - Waste management
STI/DOC/010/278
ISBN: 92-0-125387-7
Publication Date: 10-11-1987
Subject Classification: 0609 - Radiation protection; 0611 - Radioactive waste management
STI/DOC/010/279
ISBN: 92-0-155088-X
Publication Date: 22-2-1988
This guidebook provides specific advice and guidance to project management for the construction of nuclear power plants. While operating performance of nuclear power plants has been improving in recent years and has generally been comparable to or better than that of fossil fired plants in the same size ranges, performance during construction has been variable. Although additional licensing requirements, public intervention and funding problems have been blamed for most of the delays and cost increases, there is growing recognition that lack of proper project management has been a major factor. Contents: Introduction; Project management preparatory phase; Project management execution phase; Appendix I: Sample outline of project manual; Appendix II: Manpower for utility project management; Appendix III. Manpower for main contractor project management; Appendix IV. Computerized treatment of project schedules; Bibliography; Glossary.
Subject Classification: 0701 - Nuclear power planning and economics
STI/DOC/010/280
ISBN: 92-0-125088-6
Publication Date: 6-4-1988
Subject Classification: 0609 - Radiation protection
STI/DOC/010/281
ISBN: 92-0-155188-6
Publication Date: 18-4-1988
Subject Classification: 0603 - Nuclear power plants; 0701 - Nuclear power planning and economics
STI/DOC/010/282
ISBN: 92-0-155288-2
Publication Date: 9-5-1988
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/DOC/010/283
ISBN: 92-0-125188-2
Publication Date: 20-6-1988
This report serves as a guide for the planning and implementation of radiation protection programmes for all types of positive ion accelerators. The basic types of accelerators are briefly described, followed by a detailed description of several installations covering the energy range from 10 MeV to 500 GeV. Special emphasis is given to the production of ionizing radiation and its transmission through shielding, computer techniques for shield design, radiation measurement and interpretation, and the radiological impact of accelerators on the environment. Extensive references are given so the book can serve as a source to the published literature. Contents: Introduction; Characteristics of positive ion accelerators; Radiation environment of positive ion accelerators; Radiation measurements at accelerators; Radiation shielding; Accelerator radiation safety programme; Radiological environmental impact of accelerators; Sources of information and bibliography on accelerator radiation protection.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0605 - Radiation sources and accelerators; 0609 - Radiation protection
STI/DOC/010/284
ISBN: 92-0-145088-5
Publication Date: 21-6-1988
The intention has been to introduce the concepts and methods of uranium exploration geochemistry in sufficient detail so that the user may make effective use of the techniques. Contents: Chapter 1. Geochemical exploration for uranium; Chapter 2. General chemistry and geochemistry of uranium; Chapter 3. Exploration strategy; Chapter 4. Sample media and sampling techniques; Chapter 5. Sample preparation and storage; Chapter 6. Geochemical analysis for uranium; Chapter 7. Data and map preparation; Chapter 8. Interpretation of geochemical surveys; Annex I. Data recording instructions; Annex ll. Analytical procedures for fluorimetric determination of labile uranium.
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/DOC/010/286
ISBN: 92-0-125288-9
Publication Date: 26-9-1988
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/287
ISBN: 92-0-125388-5
Publication Date: 30-9-1988
Subject Classification: 0804 - Waste management
STI/DOC/010/288
ISBN: 92-0-125488-1
Publication Date: 21-9-1988
In revising the definition of high level radioactive waste unsuitable for dumping at sea, calculations of water concentrations in and near a dump site have been made and used to estimate doses to typical marine species living at or near the sea floor at a depth of 4000 m. These calculations show that there are radionuclides that can give rise to significant doses to these typical species and that future revisions of the Definition and Recommendations under the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter will have to consider impacts on the marine ecosystem in setting limits for dumping. Contents: 1. Introduction; 2. Nature of the deep sea ecosystem; 3. Naturally occurring and fallout radionuclides in the marine environment; 4. Effects of radiation on aquatic organisms; 5. Methods of dosimetry for aquatic organisms and an estimate of the background dose rate in the deep sea; 6. Derivation of dose rates to organisms based on the IAEA definition of high level radioactive waste unsuitable for dumping at sea; 7. Dose rates arising from actual sea dumping operations; 8. Summary and conclusions; Appendix: Equations and parameters used for calculations and results.
Subject Classification: 0611 - Radioactive waste management; 0612 - Safety analysis; 1300 - Environment
STI/DOC/010/289
ISBN: 92-0-125588-8
Publication Date: 1-12-1988
The conversion of treated radioactive wastes by solidification to obtain stable forms is an important step in waste management because in this way the potential for radioactivity release to the environment during storage, transportation and disposal can be minimized. This report reviews current practices in the immobilization of low and intermediate level radioactive wastes with polymers as well as new and promising research and development in this field. Some background information on the properties of polymers is given. Contents: 1. Introduction; 2. Characteristics and sources of low and intermediate level radioactive wastes; 3. Characterization of polymers; 4. Pre-treatment of wastes before immobilization; 5. Immobilization processes; 6. Conclusions.
Subject Classification: 0804 - Waste management
STI/DOC/010/290
ISBN: 92-0-155388-9
Publication Date: 10-11-1988
Subject Classification: 0603 - Nuclear power plants; 0803 - Spent fuel management
STI/DOC/010/291
ISBN: 92-0-125688-4
Publication Date: 13-1-1989
The immobilization of high level liquid wastes from the repro-cessing of irradiated nuclear fuels is of great interest, and serious efforts are being undertaken to find a satisfactory technical solution. Volatilization of fission product elements during immobilization poses the potential for the release of radioactive substances to the environment and necessitates effective off-gas cleaning systems. This report describes typical off-gas cleaning systems used in the most advanced high level liquid waste immobilization plants and considers most of the aerosols and volatile contaminants. Contents: 1. Introduction; 2. Nature of high level liquid waste (HLLW); 3. HLLW solidification processes and their application; 4. Sources and characteristics of off-gas contaminants; 5. Equipment used in off-gas treatment systems; 6. Typical off-gas systems and their performance; 7. Safety considerations; 8. Conclusions.
Subject Classification: 0804 - Waste management
STI/DOC/010/292
ISBN: 92-0-125788-0
Publication Date: 9-2-1989
Ventilation and air cleaning systems are a vital part of the general design of any nuclear facility. The combination of a well designed ventilation system with thorough cleaning of exhaust air is the main method of preventing radioactive contamination of the air in working areas and in the surrounding atmosphere. This report provides the latest information on the design and operation of off-gas cleaning and ventilation systems for designers and regulatory authorities in the control and operation of such systems in nuclear establishments. Contents: 1. Scope; 2. General purposes of off-gas cleaning and ventilation systems; 3. Health and safety requirements for design of off-gas cleaning and ventilation systems in nuclear facilities; 4. System design; 5. Typical containment, ventilation systems and components; 6. Filter properties; 7. Filter testing methods; 8. Conclusions; Annex: Standards and Rules.
Subject Classification: 0804 - Waste management
STI/DOC/010/293
Publication Date: 9-2-1989
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/294
ISBN: 92-0-125089-4
Publication Date: 9-2-1989
Solid and liquid organic radioactive wastes are generated from nuclear fuel cycle facilities and nuclear research centres, from certain uses of radioisotopes in medicine, and from research and development in other fields. Compared to other radioactive wastes, the volume of organic wastes generated is small; nevertheless they require a waste management strategy for safe handling, processing and final disposal. This report presents a review of the latest technical information available on options for the treatment and conditioning of organic radioactive wastes. Contents: 1. Introduction; 2. Waste characterization; 3. Waste management strategies; 4. Treatment and immobilization options; 5. Characterization of conditioned organic wastes; 6. Conclusions.
Subject Classification: 0804 - Waste management
STI/DOC/010/296
ISBN: 92-0-155089-8
Publication Date: 25-4-1989
Guidance in the organization and performance of regulatory inspection functions regarding the implementation of quality assurance programmes in all stages of the nuclear power plant project. The manual is intended primarily for the management personnel and upper staff from regulatory bodies but it will also be helpful to management personnel from nuclear utilities and vendors. Contents: 1. Introduction; 2. Techniques and methods of inspection; 3. Performance of regulatory inspections of quality assurance programmes; 4. Inspection reports; 5. Periodic evaluation of effectiveness of and trends in quality assurance programme performance; 6. Enforcement of compliance with the quality assurance programme; 7. Manpower requirements and technical qualifications of quality assurance regulatory inspectors; Appendix I: Inspection procedure on document control; Appendix II: Inspection procedure on procurement control; Appendix III: Inspection procedure on receipt, storage and handling of materials and equipment; Appendix IV: Inspection procedure on control of measuring and test equipment; Appendix V: Inspection procedure on non-conformance control; Appendix VI: Inspection procedure on corrective action; Appendix VII: Inspection procedure on record system; Appendix VIII: Inspection procedure on auditing; Annex I: Example of inspection report cover page for licensee inspection; Annex II: Example of inspection report cover page for vendor inspection; Annex III: Example of legal framework for enforcement measures; Annex IV: Example of severity level categorization for enforcement purposes; Annex V: Example of a system of civil penalties for enforcement purposes.
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/DOC/010/297
ISBN: 92-0-155289-0
Publication Date: 1-6-1989
In the nuclear industry, flow induced vibrations are assessed early in the design process and the results are incorporated in the design procedures. This report is a general survey of experimental and calculational methods in this area of structural mechanics. It was written by Dr. R.J. Gibert of CEA, France. Contents: 1. Introduction; 2. Scope; 3. Fluidelastic phenomena: General description; 4. Methods used for the prediction of LMFBR vibrations; 5. Impact on the design; 6. Measurement and vibrational monitoring; 7. Conclusions and recommendations; References.
Subject Classification: 0703 - Reactor technology; 1400 - Physical protection of radioactive material
STI/DOC/010/298
ISBN: 92-0-155189-4
Publication Date: 17-5-1989
This guidebook summarizes the experience of individual countries on the role of the R&D organization in developing their nuclear power programmes. Contents: 1. Introduction; 2. The role of the R&D organization; 3. Establishing the R&D organization; 4. Managing the R&D organization; References; Appendix I: The role of R&D in developing Canadas nuclear power programmes; Appendix II: Indian experience in R&D activities for nuclear power; Appendix III: Spanish experience in R&D activities for the nuclear power programme; Appendix IV: The United Kingdom Atomic Energy Authority and the United Kingdom Nuclear Power Programme; Appendix V: The Electric Power Research Institute and its nuclear R&D programme.
Subject Classification: 0701 - Nuclear power planning and economics
STI/DOC/010/299
ISBN: 92-0-155389-7
Publication Date: 10-8-1989
Improvements in water reactor fuel technology and utilization are of great importance in achieving better reactor operational safety and economics. This report is intended to provide general information on the progress made in water reactor fuel design, fabrication and utilization, as well as on current and future developments. Contents: 1. Introduction; 2. The nuclear fuel cycle; 3. Fuel and fuel element fabrication; 4. Quality control; 5. Fuel element design and performance; 6. Major developments and water reactor fuel performance experience in selected countries; 7. Fuel management: Incentives to improve fuel utilization; 8. Conclusions.
Subject Classification: 0802 - Fuel fabrication and performance
STI/DOC/010/300
ISBN: 92-0-125289-7
Publication Date: 7-9-1989
Experience at Chernobyl showed that the main long term radiological consequence to the population will probably be external exposure from radiaoctive fallout deposited on the ground. The present text provides an overview of the methodology and technology available for cleaning up large areas and gives preliminary guidance on the planning, implementation and management of such cleanups. Contents: 1. Introduction; 2. Purposes of the report; 3. Scope; 4. Planning the cleanup; 5. Managing the cleanup; 6. Characterizing the affected area; 7. Deposition of contamination on surfaces; 8. Characterizing the contamination; 9. Stabilization of contamination; 10. Decontamination techniques and equipment; 11. Interdiction of an area; 12. Application of cleanup technology to situations involving high radiation fields; 13. Loading and transporting large volumes of wastes; 14. Disposal of large volumes of wastes; 15. Radiation protection and safety; 16. Conclusions and recommendations; Annex A. The cleanup after the accident at the Chernobyl nuclear power plant.
Subject Classification: 0610 - Accident response; 0804 - Waste management
STI/DOC/010/301
ISBN: 92-0-155489-3
Publication Date: 13-10-1989
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/DOC/010/302
ISBN: 92-0-125389-3
Publication Date: 2-11-1989
The field of gaseous effluent treatment systems for incinerators is wide ranging. Efficient treatment systems extract contaminated air process gases and retain them by physical or chemical means. Off-gas cleaning systems have been developed to a high technical standard. The primary purpose of this publication is to describe the current design of off-gas cleaning technologies used in incinerator facilities for low level solid and liquid wastes. Contents: 1. Introduction; 2. Waste characteristics; 3. Incinerator types and characteristics of off-gas streams; 4. Environmental and regulatory considerations; 5. General descriptions of technologies for off-gas treatment; 6. Component design aspects and performance characteristics; 7. Summary of individual systems and operational experience; 8. Safety and operational upset conditions; 9. Problems and development needs; 10. Conclusions; Appendix A: Individual systems and operational experience.
Subject Classification: 0804 - Waste management
STI/DOC/010/304
ISBN: 92-0-125489-X
Publication Date: 13-10-1989
A unique and scientifically most difficult aspect of predictive safety analysis of repositories for long lived wastes is the extrapolation of short term field and laboratory data to the long periods of time required by regulatory agencies for performance assessment. Natural analogues may be the only way of obtaining data on the cumulative effect of the migration of radionuclides over the time-scales of interest. This report briefly summarizes the state of the art in this field for technical specialists and may also serve as an introduction to the subject for managers. Contents: 1. Introduction; 2. Natural analogues in performance assessment; 3. Potential roles of analogues in performance assessments; 4. Analogues: Their applications and limitations; 5. Discussion of the quantitative and qualitative roles of analogues; 6. Conclusions and recommendations; Appendix A: Use of natural and archaeological analogues in performance assessment of the KBS-3 copper canister; Appendix B: The Cigar Lake uranium deposit: An analogue for nuclear fuel waste disposal; Appendix C: Uranium isotope studies combined with groundwater dating as a natural analogue.
Subject Classification: 0608 - Waste repositories; 0612 - Safety analysis
STI/DOC/010/305
ISBN: 92-0-155589-X
Publication Date: 27-11-1989
This publication contains comprehensive analyses of selected stages of the nuclear fuel cycle with an outlook to the near future and with emphasis on the advantages as well as the disadvantages of the approaches discussed. Its aim is to highlight selected subjects of international interest and establish a starting point for productive discussions on the future of the nuclear fuel cycle worldwide. Contents: Trends in the nuclear fuel cycle: Development in the 1990s and international co-operation; Uranium supply and demand: Are there reasons for anxiety? AVLIS technology: Principal advantages and problems; Use of MOX fuels: The reasons to start; Fabrication, characterization and quality control of nuclear fuel ceramics.
Subject Classification: 0800 - Nuclear fuel cycle and waste management
STI/DOC/010/306
ISBN: 92-0-155689-6
Publication Date: 11-12-1989
This guidebook describes for nuclear technicians: (1) the necessary level and content of conventional education and training; (2) the level and content of nuclear oriented education and training; (3) measures to bridge the gap between the two. The guidebook complements or is supplemented by Technical Reports Series No. 200, Manpower Development for Nuclear Power; Technical Reports Series No. 242, Qualification of Nuclear Power Plant Operations Personnel; and IAEA-TECDOC-526, Appendices to the Guidebook on the Education and Training of Technicians for Nuclear Power. This guidebook seeks to assist policy makers and planners, as well as those designing and implementing education and training programmes. Contents: Introduction; 1. Definition of technicians; 2. Planning and implementation of the E&T of technicians for nuclear power; 3. Recommended E&T requirements to enter nuclear oriented E&T; 4. Upgrading the E&T of technicans who will enter nuclear oriented E&T; 5. Education and training of teachers/trainers for a nuclear power programme; 6. Functions, tasks and number of technicians in a nuclear power programme; 7. Basic and specialized E&T for a nuclear power programme; 8. Nuclear science and engineering laboratory; 9. Mechanisms for education and training implementation.
Subject Classification: 0603 - Nuclear power plants; 0705 - Qualification and training of personnel
STI/DOC/010/307
ISBN: 92-0-125589-6
Publication Date: 3-1-1990
This report discusses the management of abnormal wastes at nuclear facilities. It is intended to give guidance to nuclear power plant operators on the technical means available to enable abnormal wastes to be managed safely, and to provide assistance in the selection of appropriate technologies and processes that can be used for abnormal situations. In addition, subjects such as pre-planning and provisions for abnormal waste management, decision making on the management of abnormal wastes and adequate waste characterization are also discussed. Contents: 1. Introduction; 2. Pre-planning; 3. Abnormal waste management decision making and planning; 4. Characterization of the wastes; 5. Decontamination; 6. Treatment of liquid wastes; 7. Treatment of gaseous wastes; 8. Treatment of solid wastes; 9. Conditioning of abnormal radioactive wastes; 10. Storage, transport and disposal; References; Annex I: Experience with abnormal wastes and their management in selected power plants; Annex II: Examples of decision making processes in the management of abnormal wastes.
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
Feasibility of Separation and Utilization of Ruthenium, Rhodium and Palladium from High Level Wastes
STI/DOC/010/308
ISBN: 92-0-145089-3
Publication Date: 3-1-1990
The fission product nuclides generated during the irradiation of reactor fuel include several useful materials, among them precious metals of the platinum group (ruthenium, rhodium and palladium) which are of great commercial importance, occur rarely in nature and are highly valuable. This report is intended mainly to provide a basis for further consideration of the options for platinum group metal recovery from high level radioactive wastes, and for the formulation of appropriate strategies. Contents: 1. Introduction; 2. Properties, uses and markets for platinum group metals; 3. Production of platinum group metals in nuclear reactors: Composition, cooling effects and amounts arising; 4. Occurrence of platinum group metals in nuclear fuel cycle operations; 5. Recovery and purification of platinum group metals from nuclear fuel reprocessing wastes; 6. Radiation safety and licensing considerations; 7. Conclusions and recommendations.
Subject Classification: 0804 - Waste management
STI/DOC/010/309
ISBN: 92-0-145189-X
Publication Date: 22-1-1990
This report describes facilities primarily designed for uranium exploration instruments, but also discusses the use of these facilities for the calibration of radiation protection instruments. Contents: 1. Introduction; 2. Basic radiation geophysics; 3. Instruments used in radiation surveys; 4. Quantities and units; 5. Relations between instrument readings and the corresponding field assay values; 6. Calibration systems; 7. Design considerations for calibration pads; 8. Construction of calibration pads; 9. Calibration.
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/DOC/010/310
ISBN: 92-0-125190-4
Publication Date: 29-3-1990
Subject Classification: 0601 - Uranium mining and milling; 1300 - Environment
STI/DOC/010/310
ISBN: 92-0-125090-8
Publication Date: 28-2-1990
Subject Classification: 0601 - Uranium mining and milling; 1300 - Environment
STI/DOC/010/312
ISBN: 92-0-155090-1
Publication Date: 8-6-1990
The present publication is an update of IAEA Technical Reports Series No. 235, Status of and Prospects for Gas-Cooled Reactors, published in 1984. It is a compilation of information based on submissions from Member States and is considered current as of the beginning of 1989. It describes the status of gas cooled reactors with specific emphasis on the design and safety characteristics of the various concepts that are either incorporated in operating reactors or in reactors being designed and considered for future construction and operation. Contents: Chapter 1. Introduction; Chapter 2. Status of international gas cooled reactor development; Chapter 3. General features of gas cooled reactors and their safety characteristics; Chapter 4. Gas cooled reactor design and safety in the United Kingdom; Chapter 5. Gas cooled reactor design and safety in the United States of America; Chapter 6. Gas cooled reactor design and safety in Japan; Chapter 7. Gas cooled reactor design and safety in the Union of Soviet Socialist Republics; Chapter 8. Gas cooled reactor design and safety in Switzerland; Chapter 9. Gas cooled reactor design and safety in the Federal Republic of Germany; Chapter 10. Summary; Annex: Information exchange on gas cooled reactors.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/DOC/010/313
ISBN: 92-0-145190-3
Publication Date: 9-8-1990
Laboratory testing of uranium ores is an essential step in the economic evaluation of uranium occurrences and in the development of a project for the production of uranium concentrates. Although these tests represent only a small proportion of the total cost of a project, their proper planning, execution and interpretation are of crucial importance. This manual discusses the objectives of metallurgical laboratory ore testing, shows the specific role of these tests in the development of a project and provides practical instructions for performing the tests and for interpreting their results. Guidelines on the design of a metallurgical laboratory, on the equipment required to perform the tests and on laboratory safety are also given. Contents: 1. Introduction; 2. Sampling and characterization; 3. Size reduction; 4. Leaching; 5. Solidliquid separation and washing; 6. Uranium recovery from leach solutions; 7. Uranium recovery by ion exchange; 8. Uranium recovery by solvent extraction; 9. Precipitation; 10. Alternative techniques; 11. Flow sheets and material balances; 12. Report writing; Appendix I: Laboratory safety; Appendix II: Guidelines for laboratory design; Appendix III: Suggested laboratory equipment and supplies.
Subject Classification: 0801 - Uranium ore processing
STI/DOC/010/314
ISBN: 92-0-145290-X
Publication Date: 15-8-1990
The design, construction and operation of a pilot plant are often important stages in the development of a project for the production of uranium concentrates. The main purpose of this guidebook is to discuss the objectives of a pilot plant and its proper role in the overall project. Since building and operating a pilot plant is very costly, it is important that such a plant be built only after several prerequisites have been met. This book discusses the rationale for a pilot plant and provides guidelines with suggested solutions for a variety of problems that may be encountered. Contents: 1. Introduction; 2. Process selection and design; 3. Basic engineering; 4. Project administration; Appendix I: Example of a uranium pilot plant; Appendix II: General and radiological safety; Annex: Basic data; References; Bibliography.
Subject Classification: 0801 - Uranium ore processing
STI/DOC/010/315
ISBN: 92-0-155190-8
Publication Date: 16-8-1990
This manual has been developed to assist plant managers in fulfilling their responsibility with regard to the control and direction of quality and quality assurance activities in nuclear power plant operation. It emphasizes quality objectives for nuclear power plant operations and gives highlighted practices complemented by typical examples of forms and procedures. The selected activities comprise those where it was felt that practical advice is generally needed. Contents: 1. Introduction; 2. Quality management; 3. Competence of personnel; 4. Operations; 5. Maintenance; 6. Deficiencies and corrective actions; 7. Technical support; 8. Radiological safety; 9. Emergency preparedness; 10. Feedback; Appendix A: Summary of plant superintendents involvement and reviews listed in the manual; Appendix B: Typical organization of nuclear power plant operations, showing the functions allocated to superintendents and managers; Annexes IXXI.
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/DOC/010/317
ISBN: 92-0-155290-4
Publication Date: 28-9-1990
This manual was developed to serve as guidance on non-conformance and corrective actions which have been identified as the major problems in the implementation of an effective quality assurance programme. The scope of this manual, while fully addressing the requirements in the governing NUSS programme documents, also covers corrective action processes which would more generally assist users in developing good practices for improved performance in all areas of safety, reliability and economics, and it offers a practical model and illustrative examples of the means by which effective measures and actions can be implemented. Contents: 1. Introduction; 2. Description of corrective action process; 3. Identification of deficiencies; 4. Assessing and correcting deficiencies; 5. Root cause analysis; 6. Verification and follow-up; 7. Implementing procedures; 8. Trend analysis; 9. Summary; Definitions; References; Annex A: Example of a hold for QA clearance tag; Annex B: Examples of non-conformance report forms; Annex C: Example of a reject tag; Annex D: Example of a checklist for reviewing non-conformance dispositions; Annex E: Examples of a stop work notice and stop work notice tag; Annex F: Examples of a deficiency report form and deficiency reportwork order forms; Annex G: Example of a list defining a significant event for a nuclear power plant; Annex H: Example of a method for evaluating personnel caused deficiencies; Annex I: Example of a procedure for escalation to higher levels of management to achieve corrective action; Annex J: Example of a status report for corrective actions; Annex K: Example of a non-conformance control implementing procedure; Annex L: Example of a corrective action request implementing procedure; Annex M: Example of an implementing procedure on tracking and trending of quality problems; Annex N: Example of a method of coding of non-conformance data for defect analysis; Annex O: Example of reports available from a defect analysis programme.
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/DOC/010/318
ISBN: 92-0-125290-0
Publication Date: 26-7-1990
Subject Classification: 0306 - Nuclear data; 0609 - Radiation protection
STI/DOC/010/319
ISBN: 92-0-125390-7
Publication Date: 30-11-1990
For high level and alpha bearing radioactive wastes, the disposal concept most generally agreed upon is the emplacement of the conditioned waste in deep underground respositories in stable geological formations. The report reflects the general consensus that long lived radioactive wastes can be isolated safely from human environment in such repositories located in deep, geological formations. One of the most important tasks in the development of underground disposal systems is the plugging of boreholes and the sealing of shafts excavated for either exploratory or operational purposes. Several countries have outlined proposals and identified geological formations for detailed examination as potential host media for waste repositories. Contents: 1. Introduction and scope; 2. Background information; 3. Performance specifications; 4. Materials and methods; 5. Longevity; 6. Design factors; 7. Design of sealing systems; 8. Performance testing; References; Glossary.
Subject Classification: 0608 - Waste repositories; 0804 - Waste management
STI/PUB/502
ISBN: 92-0-523086-3
Publication Date: 13-3-1986
Subject Classification: 0603 - Nuclear power plants
STI/PUB/503
ISBN: 92-0-523186-X
Publication Date: 17-3-1986
Subject Classification: 0603 - Nuclear power plants
STI/PUB/504
ISBN: 92-0-523486-9
Publication Date: 20-5-1986
Subject Classification: 0603 - Nuclear power plants
STI/PUB/531
ISBN: 92-0-524286-1
Publication Date: 28-11-1986
Subject Classification: 0603 - Nuclear power plants
STI/PUB/532
ISBN: 92-0-524386-8
Publication Date: 28-11-1986
Subject Classification: 0603 - Nuclear power plants
STI/PUB/533
ISBN: 92-0-523686-1
Publication Date: 18-7-1986
Subject Classification: 0603 - Nuclear power plants
STI/PUB/536
ISBN: 92-0-524586-0
Publication Date: 23-12-1986
Subject Classification: 0603 - Nuclear power plants
STI/PUB/539
ISBN: 92-0-223889-8
Publication Date: 22-1-1990
This guide deals with the dispersion of normal and accidental releases of radioactive material from nuclear power plants into surface water for a full range of releases, including steady state (routine releases), instantaneous or puff (accidental releases), and time dependent long term releases (routine or accidental releases). It describes the information needed, gives recommendations on measurement programmes and the selection and use of appropriate mathematical models for evaluating dispersion. Contents: Introduction; Information needed at the site survey stage; Information needed at the site evaluation stage; Modelling of radionuclide dispersion in surface waters; Appendix A: General discussion of radionuclide dispersion modelling in surface waters; Appendix B: Models for the initial dilution of radioactive material; Appendix C: Models for far-field radionuclide dispersion in rivers; Appendix D: Models for far-field radionuclide dispersion from open coasts; Appendix E: Models for dispersion of radionuclides in estuaries; Appendix F: Models for far-field radionuclide dispersion in impoundments; Annex I: Measurement of diffusion coefficients; Annex II: Measurement of equilibrium sediment distribution coefficients; Annex III: Examples of accuracy and sensitivity of instrumentation; Annex IV: Equations of simple models for radionuclide dispersion in rivers, open coasts, estuaries and impoundments; Annex V: Advanced models for radionuclide dispersion in rivers; Annex VI: Advanced models for radionuclide dispersion in the near shore of open coastal areas; Annex VII: Advanced models for radionuclide dispersion in estuaries; Annex VIII: Advanced models for radionuclide dispersion in impoundments; Annex IX: Deposited airborne radioactive material as a source for dispersion in surface waters.
Subject Classification: 0603 - Nuclear power plants; 1300 - Environment
STI/PUB/539
ISBN: 92-0-323187-0
Publication Date: 29-4-1987
This guide deals with the dispersion of normal and accidental releases of radioactive material from nuclear power plants into surface water for a full range of releases, including steady state (routine releases), instantaneous or puff (accidental releases), and time dependent long term releases (routine or accidental releases). It describes the information needed, gives recommendations on measurement programmes and the selection and use of appropriate mathematical models for evaluating dispersion. Contents: Introduction; Information needed at the site survey stage; Information needed at the site evaluation stage; Modelling of radionuclide dispersion in surface waters; Appendix A: General discussion of radionuclide dispersion modelling in surface waters; Appendix B: Models for the initial dilution of radioactive material; Appendix C: Models for far-field radionuclide dispersion in rivers; Appendix D: Models for far-field radionuclide dispersion from open coasts; Appendix E: Models for dispersion of radionuclides in estuaries; Appendix F: Models for far-field radionuclide dispersion in impoundments; Annex I: Measurement of diffusion coefficients; Annex II: Measurement of equilibrium sediment distribution coefficients; Annex III: Examples of accuracy and sensitivity of instrumentation; Annex IV: Equations of simple models for radionuclide dispersion in rivers, open coasts, estuaries and impoundments; Annex V: Advanced models for radionuclide dispersion in rivers; Annex VI: Advanced models for radionuclide dispersion in the near shore of open coastal areas; Annex VII: Advanced models for radionuclide dispersion in estuaries; Annex VIII: Advanced models for radionuclide dispersion in impoundments; Annex IX: Deposited airborne radioactive material as a source for dispersion in surface waters.
Subject Classification: 0603 - Nuclear power plants; 1300 - Environment
STI/PUB/539
ISBN: 92-0-423587-X
Publication Date: 9-11-1987
This guide deals with the dispersion of normal and accidental releases of radioactive material from nuclear power plants into surface water for a full range of releases, including steady state (routine releases), instantaneous or puff (accidental releases), and time dependent long term releases (routine or accidental releases). It describes the information needed, gives recommendations on measurement programmes and the selection and use of appropriate mathematical models for evaluating dispersion. Contents: Introduction; Information needed at the site survey stage; Information needed at the site evaluation stage; Modelling of radionuclide dispersion in surface waters; Appendix A: General discussion of radionuclide dispersion modelling in surface waters; Appendix B: Models for the initial dilution of radioactive material; Appendix C: Models for far-field radionuclide dispersion in rivers; Appendix D: Models for far-field radionuclide dispersion from open coasts; Appendix E: Models for dispersion of radionuclides in estuaries; Appendix F: Models for far-field radionuclide dispersion in impoundments; Annex I: Measurement of diffusion coefficients; Annex II: Measurement of equilibrium sediment distribution coefficients; Annex III: Examples of accuracy and sensitivity of instrumentation; Annex IV: Equations of simple models for radionuclide dispersion in rivers, open coasts, estuaries and impoundments; Annex V: Advanced models for radionuclide dispersion in rivers; Annex VI: Advanced models for radionuclide dispersion in the near shore of open coastal areas; Annex VII: Advanced models for radionuclide dispersion in estuaries; Annex VIII: Advanced models for radionuclide dispersion in impoundments; Annex IX: Deposited airborne radioactive material as a source for dispersion in surface waters.
Subject Classification: 0603 - Nuclear power plants; 1300 - Environment
STI/PUB/539
ISBN: 92-0-123285-3
Publication Date: 26-3-1985
This guide deals with the dispersion of normal and accidental releases of radioactive material from nuclear power plants into surface water for a full range of releases, including steady state (routine releases), instantaneous or puff (accidental releases), and time dependent long term releases (routine or accidental releases). It describes the information needed, gives recommendations on measurement programmes and the selection and use of appropriate mathematical models for evaluating dispersion. Contents: Introduction; Information needed at the site survey stage; Information needed at the site evaluation stage; Modelling of radionuclide dispersion in surface waters; Appendix A: General discussion of radionuclide dispersion modelling in surface waters; Appendix B: Models for the initial dilution of radioactive material; Appendix C: Models for far-field radionuclide dispersion in rivers; Appendix D: Models for far-field radionuclide dispersion from open coasts; Appendix E: Models for dispersion of radionuclides in estuaries; Appendix F: Models for far-field radionuclide dispersion in impoundments; Annex I: Measurement of diffusion coefficients; Annex II: Measurement of equilibrium sediment distribution coefficients; Annex III: Examples of accuracy and sensitivity of instrumentation; Annex IV: Equations of simple models for radionuclide dispersion in rivers, open coasts, estuaries and impoundments; Annex V: Advanced models for radionuclide dispersion in rivers; Annex VI: Advanced models for radionuclide dispersion in the near shore of open coastal areas; Annex VII: Advanced models for radionuclide dispersion in estuaries; Annex VIII: Advanced models for radionuclide dispersion in impoundments; Annex IX: Deposited airborne radioactive material as a source for dispersion in surface waters.
Subject Classification: 0603 - Nuclear power plants; 1300 - Environment
STI/PUB/542
ISBN: 92-0-524086-7
Publication Date: 9-10-1986
This guide recommends how to classify structures, systems and components according to their importance to safety. The classification is translated into graded safety requirements that in turn influence the design. Twenty safety functions are listed and the methodology outlined ranks them according to their importance to safety. Contents: Introduction; Safety functions; Ranking of safety functions; Assignment of safety class requirements; Appendix A: Design requirements for structural integrity of boundaries of fluid-retaining components.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/545
ISBN: 92-0-523586-5
Publication Date: 20-5-1986
Subject Classification: 0603 - Nuclear power plants
STI/PUB/549
ISBN: 92-0-523886-4
Publication Date: 12-8-1986
The guide addresses the meteorological investigations needed at different stages in a site survey, in site evaluation and in assessing off-site consequences of operational states and accident conditions. It covers meteorological phenomena and mechanisms involved in the dispersion of radioactive effluents, calculation methods for concentration and deposition, input data needed for calculations, meteorological instrumentation requirements, data analysis system requirements and other related topics. Contents: Introduction; On-site and off-site meteorological investigation programme; Atmospheric dispersion models; Average short-term concentration estimates; Meteorological aspects of emergency planning at nuclear power plants; Annex I: Turbulence and atmospheric dispersion; Annex II: Atmospheric stability; Annex III: Equivalent height of plume Dh (non-buoyant plume); Annex IV: Examples of simplified models; Annex V: A direct method for determining stability class (Pasquill method and modifications); Annex VI: Dependence of concentration on sampling time; Annex VII: Modified Bulk Richardson number method for sy and sz; Annex VIII: Additional graphs for sy and sz.
Subject Classification: 0603 - Nuclear power plants; 1300 - Environment
STI/PUB/551
ISBN: 92-0-523588-1
Publication Date: 12-10-1988
This guide gives design guidance on requirements for the protection system which monitors the relevant plant variables and performs - in conjunction with the safety actuation systems and safety system support features - all safety tasks that may become necessary when unacceptable. Contents: Introduction; Extent of the protection system; General design principles; Safety system monitoring; Safety actuation systems and safety system support features; Design verification; System documentation; Annex I: Information on certain definitions.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/552
ISBN: 92-0-523087-1
Publication Date: 21-4-1987
This guide covers the protection of nuclear power plants against missiles that may result from failures of equipment. Missiles from sources outside the plant are not addressed. The recommendations given are intended as an aid in assessing design adequacy. Overall aspects of what constitutes adequate protection are thus more extensively elaborated than the details of how to accomplish that task. Contents: Introduction; General philosophy; Origin of missiles and appropriate design considerations; Secondary effects; Protective methods and means against missiles; Documentation requirements; Annex.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/554
ISBN: 92-0-523387-0
Publication Date: 10-9-1987
This guide deals with the commissioning of all types of nuclear power plants with thermal neutron reactors. Its purpose is to give guidance on good practice, the implementation of which will enable commissioning to proceed safely and provide assurances that the plant has been constructed and can operate according to design intent. The guide covers the programme of tests to be prepared and the responsibility for implementing and reporting on the various parts of the commissioning programme. Contents: Introduction; Commissioning programme; Principal stages of commissioning; Testing procedures; Organization, responsibilities and audit; Interfaces between construction, commissioning and operating activities at the site; Deviations during commissioning; Documentation; Appendix A: Fuel loading; Annex I: Detailed list of commissioning tests; Definitions.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/557
ISBN: 92-0-523687-X
Publication Date: 27-10-1987
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/560
ISBN: 92-0-523487-7
Publication Date: 10-9-1987
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/569
ISBN: 92-0-523188-6
Publication Date: 8-6-1988
This guide presents population distribution data requirements, examples of territory screening and various approaches to evaluating population distribution and site selection. It also gives an overview of radiological impact assessment with respect to population data (current and projected), data format (concentric rings and sectors) and supplementary site information. Contents: Introduction; Data requirements; Territory screening and preliminary site selection methods; Radiological impact and final site evaluation; Annex I: Histograms of population distribution around some nuclear power plant sites; Annex II: Details of methods described in Section 3; Annex III: Suggested bases for choice of method.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/571
ISBN: 92-0-523488-5
Publication Date: 8-6-1988
This guide discusses the review and assessment process, as well as the various relationships between the regulatory body and the applicant/licensee, the applicant/licensee's vendor, other governmental bodies, and consultants and advisory committees. It covers the specific stages of the licensing process, i.e. siting, construction, commissioning, operation and decommissioning. Contents: Introduction; Objectives of the review and assessment process; General relationships in the review and assessment process; Exchange of information; Areas for review and assessment; Bases for review and assessment; Method of review and assessment; International co-operation in review and assessment.
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/574
ISBN: 92-0-523187-8
Publication Date: 21-4-1987
This guide deals with the commissioning of all types of nuclear power plants with thermal neutron reactors. Its purpose is to give guidance on good practice, the implementation of which will enable commissioning to proceed safely and provide assurances that the plant has been constructed and can operate according to design intent. The guide covers the programme of tests to be prepared and the responsibility for implementing and reporting on the various parts of the commissioning programme. Contents: Introduction; Commissioning programme; Principal stages of commissioning; Testing procedures; Organization, responsibilities and audit; Interfaces between construction, commissioning and operating activities at the site; Deviations during commissioning; Documentation; Appendix A: Fuel loading; Annex I: Detailed list of commissioning tests; Definitions.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/577
ISBN: 92-0-524186-3
Publication Date: 9-10-1986
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/581
ISBN: 92-0-523287-4
Publication Date: 23-6-1987
The ultimate heat sink and its directly associated heat transport systems addressed in this guide are required to remove residual heat from the core after reactor shutdown, and during and after appropriate operational states and accident conditions. The guide covers design considerations for various types of ultimate heat sinks and the directly associated heat transport systems, and for various types and sources of related heat transport fluids. Contents: Introduction; Design principles; Postulated initiating events; Design features; Annex I: Typical configurations of an ultimate heat sink and its directly associated heat transport systems; Annex II: Typical events to be considered for credible combinations in establishing postulated initiating events for design of UHS.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/585
ISBN: 92-0-523590-3
Publication Date: 27-9-1990
This guide discusses the hazardous phenomena associated with external man-induced events, such as aircraft crashes, explosions, release of hazardous fluids using screening distances and probabilities. Their potential effects on the nuclear power plant and methods used to develop adequate design bases for the plant to prevent such effects are also included. Contents: Introduction; Potential sources of man-induced events and associated features; Collection of information and evaluation; Administrative aspects; Preliminary screening and detailed evaluations; Aircraft crashes; Explosions; Release of hazardous fluids; Other man-induced events; Annex I: Aircraft crashes; Annex II: Chemical explosions; Annex III: Hazards from drifting clouds; Annex IV: Fire.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/587
ISBN: 92-0-523288-2
Publication Date: 8-6-1988
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/601
ISBN: 92-0-523587-3
Publication Date: 27-10-1987
The guide deals with emergency arrangements for which public authorities are responsible, the interaction with the operating organization emergency plan and the integration into the overall emergency planning. Guidance is given on the main aspects of assigning responsibility to public authorities, the regulatory body and the operating organization. Contents: Introduction; Range of accidents to be considered in emergency planning; Responsibilities for emergency planning, organizing and action; Emergency organization; Emergency planning; Emergency assessments and protective measures; Public information and instruction; Training and exercises; Co-operation across boundaries; Annexes.
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response; 0614 - Legal and governmental aspects
STI/PUB/605
ISBN: 92-0-524486-4
Publication Date: 28-11-1986
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/606
ISBN: 92-0-524188-1
Publication Date: 20-1-1989
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/631
ISBN: 92-0-523788-4
Publication Date: 12-10-1988
Subject Classification: 0603 - Nuclear power plants
STI/PUB/634
ISBN: 92-0-523688-8
Publication Date: 12-10-1988
Subject Classification: 0603 - Nuclear power plants
STI/PUB/637
ISBN: 92-0-523089-8
Publication Date: 29-3-1989
Subject Classification: 0601 - Uranium mining and milling; 0609 - Radiation protection
STI/PUB/644
ISBN: 92-0-523388-9
Publication Date: 8-6-1988
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/654
ISBN: 92-0-523088-X
Publication Date: 17-3-1988
This guide deals with the protection of site personnel and general public from the effects of ionizing radiation. It outlines how radiation protection on-site for all operational states of the plant, accident conditions and emergency situations can be implemented. Among the organizational aspects dealt with are the duties and responsibilities of the operating organization, the plant management and the health physics group. Contents: Introduction; Basic principles of radiation protection; Organizational aspects; Practical aspects of implementation of a radiation protection programme; Effluent release, radioactive waste disposal and environmental monitoring; Storage, handling and transport of radioactive materials; Training; Facilities and equip-ment; Records; Annex I: Explanatory notes on radiation protection terms and concepts used in this Guide; Annex II: Some specific limits and requirements summarized from publications of the ICRP.
Subject Classification: 0603 - Nuclear power plants; 0609 - Radiation protection
STI/PUB/654
ISBN: 92-0-423285-4
Publication Date: 8-7-1985
This guide deals with the protection of site personnel and general public from the effects of ionizing radiation. It outlines how radiation protection on-site for all operational states of the plant, accident conditions and emergency situations can be implemented. Among the organizational aspects dealt with are the duties and responsibilities of the operating organization, the plant management and the health physics group. Contents: Introduction; Basic principles of radiation protection; Organizational aspects; Practical aspects of implementation of a radiation protection programme; Effluent release, radioactive waste disposal and environmental monitoring; Storage, handling and transport of radioactive materials; Training; Facilities and equip-ment; Records; Annex I: Explanatory notes on radiation protection terms and concepts used in this Guide; Annex II: Some specific limits and requirements summarized from publications of the ICRP.
Subject Classification: 0603 - Nuclear power plants; 0609 - Radiation protection
STI/PUB/655
ISBN: 92-0-423085-1
Publication Date: 21-5-1985
Sites vulnerable to coastal flooding are located on open coastal regions directly exposed to or having a shore on a major body of water, semi-enclosed bodies of water such as lagoons, estuaries, rivers, fjords and rias, or enclosed bodies of water such as lakes and reservoirs. Floods due to waves, surges, seiches and tsunamis are discussed, including ways to combine the effects of these to calculate design values for run-up and draw-down. Contents: Introduction; Preliminary investigation; Detailed information; Flooding by storm surges and seiches; Tsunami flooding; Wave effects; Reference water level; Ice effects; Combined flooding events; Design basis for the flood; Shoreline stability; Flood protection aspects of nuclear power plant siting; Monitoring and warning for plant protection; Appendix A: Stochastic methodologies in surge analysis; Annex I: Probable maximum storm characteristics and storm surge analysis; Annex II: Frequency distribution functions; Annex III: Tsunami evaluation; Annex IV: Nearshore wave effects; Annex V: Example of possible combinations of flood-causing events; Annex VI: Monitoring and warning systems.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/660
ISBN: 92-0-423386-9
Publication Date: 26-5-1986
The basic safety approach of defence in depth and high functional system availability is addressed in this guide. Attention is also paid to the safety implications of operator actions and their consideration in the design. Contents: Introduction; Scope; Safety principles; Safety approach; Design requirements; Safety analysis; Equipment qualification; Quality assurance; Appendix A: Postulated initiating events (PIEs); Annex I: Safety principles used in the development of NUSS documents; Annex II: Typical listings for the compilation of postulated initiating events; Annex III: List of safety functions from IAEA Safety Series No. 50-SG-D1.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/660
ISBN: 92-0-323085-8
Publication Date: 6-3-1985
The basic safety approach of defence in depth and high functional system availability is addressed in this guide. Attention is also paid to the safety implications of operator actions and their consideration in the design. Contents: Introduction; Scope; Safety principles; Safety approach; Design requirements; Safety analysis; Equipment qualification; Quality assurance; Appendix A: Postulated initiating events (PIEs); Annex I: Safety principles used in the development of NUSS documents; Annex II: Typical listings for the compilation of postulated initiating events; Annex III: List of safety functions from IAEA Safety Series No. 50-SG-D1.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/662
ISBN: 92-0-323185-4
Publication Date: 30-7-1985
The basic safety approach of defence in depth and high functional system availability is addressed in this guide. Attention is also paid to the safety implications of operator actions and their consideration in the design. Contents: Introduction; Scope; Safety principles; Safety approach; Design requirements; Safety analysis; Equipment qualification; Quality assurance; Appendix A: Postulated initiating events (PIEs); Annex I: Safety principles used in the development of NUSS documents; Annex II: Typical listings for the compilation of postulated initiating events; Annex III: List of safety functions from IAEA Safety Series No. 50-SG-D1.
Subject Classification: 0602 - Fuel fabrication and storage; 0603 - Nuclear power plants
STI/PUB/662
ISBN: 92-0-423385-0
Publication Date: 8-7-1985
The basic safety approach of defence in depth and high functional system availability is addressed in this guide. Attention is also paid to the safety implications of operator actions and their consideration in the design. Contents: Introduction; Scope; Safety principles; Safety approach; Design requirements; Safety analysis; Equipment qualification; Quality assurance; Appendix A: Postulated initiating events (PIEs); Annex I: Safety principles used in the development of NUSS documents; Annex II: Typical listings for the compilation of postulated initiating events; Annex III: List of safety functions from IAEA Safety Series No. 50-SG-D1.
Subject Classification: 0602 - Fuel fabrication and storage; 0603 - Nuclear power plants
STI/PUB/663
ISBN: 92-0-524088-5
Publication Date: 20-1-1989
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/663
ISBN: 92-0-423185-8
Publication Date: 21-5-1985
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/666
ISBN: 92-0-323186-2
Publication Date: 2-4-1986
This guide describes first the general characteristics of tropical cyclones with particular emphasis on their pressure and wind structures. The collection of information, the data sources and requirements are treated in some detail. The subsequent sections deal with a description of the procedures available for evaluating the probable maximum tropical cyclone (PMTC), including deterministic and probabilistic approaches for determining the pressure at the eye of a tropical cyclone. Contents: Introduction; Collection of information; Procedures for evaluating the PMTC; Evaluation of other parameters needed to define the PMTC wind field; Determination of the PMTC wind field; Annex I: Tropical cyclone nomenclature; Annex II: Background for the development of the deterministic method; Annex III: Deterministic approach to p0; Annex IV: Examples of estimating p0 for the South China Sea region by the probabilistic method; Annex V: p0 relations with heights of pressure levels; Annex VI: Example for evaluation of limits for miminum R for the Probable Maximum Hurricane (PMH) for the tropical North Atlantic (abstract from Schwerdt et al.); Annex VII: Derivation of equations for computing the maximum gradient wind speed.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/666
ISBN: 92-0-423186-6
Publication Date: 4-3-1986
This guide describes first the general characteristics of tropical cyclones with particular emphasis on their pressure and wind structures. The collection of information, the data sources and requirements are treated in some detail. The subsequent sections deal with a description of the procedures available for evaluating the probable maximum tropical cyclone (PMTC), including deterministic and probabilistic approaches for determining the pressure at the eye of a tropical cyclone. Contents: Introduction; Collection of information; Procedures for evaluating the PMTC; Evaluation of other parameters needed to define the PMTC wind field; Determination of the PMTC wind field; Annex I: Tropical cyclone nomenclature; Annex II: Background for the development of the deterministic method; Annex III: Deterministic approach to p0; Annex IV: Examples of estimating p0 for the South China Sea region by the probabilistic method; Annex V: p0 relations with heights of pressure levels; Annex VI: Example for evaluation of limits for miminum R for the Probable Maximum Hurricane (PMH) for the tropical North Atlantic (abstract from Schwerdt et al.); Annex VII: Derivation of equations for computing the maximum gradient wind speed.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/666
ISBN: 92-0-223385-3
Publication Date: 9-9-1985
This guide describes first the general characteristics of tropical cyclones with particular emphasis on their pressure and wind structures. The collection of information, the data sources and requirements are treated in some detail. The subsequent sections deal with a description of the procedures available for evaluating the probable maximum tropical cyclone (PMTC), including deterministic and probabilistic approaches for determining the pressure at the eye of a tropical cyclone. Contents: Introduction; Collection of information; Procedures for evaluating the PMTC; Evaluation of other parameters needed to define the PMTC wind field; Determination of the PMTC wind field; Annex I: Tropical cyclone nomenclature; Annex II: Background for the development of the deterministic method; Annex III: Deterministic approach to p0; Annex IV: Examples of estimating p0 for the South China Sea region by the probabilistic method; Annex V: p0 relations with heights of pressure levels; Annex VI: Example for evaluation of limits for miminum R for the Probable Maximum Hurricane (PMH) for the tropical North Atlantic (abstract from Schwerdt et al.); Annex VII: Derivation of equations for computing the maximum gradient wind speed.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/667
ISBN: 92-0-423187-4
Publication Date: 24-4-1987
Subject Classification: 0604 - Research reactors
STI/PUB/667
ISBN: 92-0-323485-3
Publication Date: 31-12-1985
Subject Classification: 0604 - Research reactors
STI/PUB/667
ISBN: 92-0-223485-X
Publication Date: 27-11-1985
Subject Classification: 0604 - Research reactors
STI/PUB/673
ISBN: 92-0-020185-7
Publication Date: 22-7-1985
Subject Classification: 0603 - Nuclear power plants
STI/PUB/674
ISBN: 92-0-020085-0
Publication Date: 17-6-1985
Subject Classification: 0609 - Radiation protection; 0612 - Safety analysis
STI/PUB/676
ISBN: 92-0-323086-6
Publication Date: 2-4-1986
The guide provides information, guidance and recommendations to assist a regulatory body in establishing regulations that are compulsory, and in developing guides that are advisory. The NUSS programme, which is based on regulations and guides in Member States, is presented as a frame of reference for safety. The system of regulations and guides required in Member States having a nuclear power programme is given, starting with basic legislation. The book covers regulations and guides extensively, citing industrial standards and pointing out interrelationships and differences between them. Contents: Introduction; IAEA NUSS programme; System of regulations and guides; Programme of regulations and guides; Establishment of regulations; Establishment of guides; Annex 1: Framework of regulatory documents in certain Member States.
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/676
ISBN: 92-0-423086-X
Publication Date: 20-2-1986
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/676
ISBN: 92-0-223285-7
Publication Date: 25-9-1985
The guide provides information, guidance and recommendations to assist a regulatory body in establishing regulations that are compulsory, and in developing guides that are advisory. The NUSS programme, which is based on regulations and guides in Member States, is presented as a frame of reference for safety. The system of regulations and guides required in Member States having a nuclear power programme is given, starting with basic legislation. The book covers regulations and guides extensively, citing industrial standards and pointing out interrelationships and differences between them. Contents: Introduction; IAEA NUSS programme; System of regulations and guides; Programme of regulations and guides; Establishment of regulations; Establishment of guides; Annex 1: Framework of regulatory documents in certain Member States.
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/677
ISBN: 92-0-323586-8
Publication Date: 15-5-1986
This guide deals with the determination of the radionuclide concentration in groundwater resulting from postulated releases from nuclear power plants. The main emphasis is on the behaviour of radioactive material in groundwater and on the methods forassessing the radionuclide movement in various aquifers. This movement of radionuclides in the ground is essentially controlled by the phenomena of transport (bulk motion of groundwater), hydrodynamic dispersion (spread of contaminate front) and ion exchange. Contents: Introduction; Site survey stage; Site evaluation stage; Modelling of radionuclide dispersion and retention in groundwater; Groundwater monitoring programme; Appendix A: Modelling of radionuclide movement in groundwater; Annex I: Considerations related to groundwater availability; Annex II: Analytical solutions of the advective transport and hydrodynamic dispersion equations; Annex III: Accuracy and reliability of measurements in hydrogeology; Annex IV: Examples of methods and frequencies of measurements within the monitoring programme; Special definitions.
Subject Classification: 0603 - Nuclear power plants; 1300 - Environment
STI/PUB/677
ISBN: 92-0-423486-5
Publication Date: 13-10-1986
This guide deals with the determination of the radionuclide concentration in groundwater resulting from postulated releases from nuclear power plants. The main emphasis is on the behaviour of radioactive material in groundwater and on the methods for assessing the radionuclide movement in various aquifers. This movement of radionuclides in the ground is essentially controlled by the phenomena of transport (bulk motion of groundwater), hydrodynamic dispersion (spread of contaminate front) and ion exchange. Contents: Introduction; Site survey stage; Site evaluation stage; Modelling of radionuclide dispersion and retention in groundwater; Groundwater monitoring programme; Appendix A: Modelling of radionuclide movement in groundwater; Annex I: Considerations related to groundwater availability; Annex II: Analytical solutions of the advective transport and hydrodynamic dispersion equations; Annex III: Accuracy and reliability of measurements in hydrogeology; Annex IV: Examples of methods and frequencies of measurements within the monitoring programme; Special definitions.
Subject Classification: 0603 - Nuclear power plants; 1300 - Environment
STI/PUB/677
ISBN: 92-0-223286-5
Publication Date: 23-5-1986
This guide deals with the determination of the radionuclide concentration in groundwater resulting from postulated releases from nuclear power plants. The main emphasis is on the behaviour of radioactive material in groundwater and on the methods forassessing the radionuclide movement in various aquifers. This movement of radionuclides in the ground is essentially controlled by the phenomena of transport (bulk motion of groundwater), hydrodynamic dispersion (spread of contaminate front) and ion exchange. Contents: Introduction; Site survey stage; Site evaluation stage; Modelling of radionuclide dispersion and retention in groundwater; Groundwater monitoring programme; Appendix A: Modelling of radionuclide movement in groundwater; Annex I: Considerations related to groundwater availability; Annex II: Analytical solutions of the advective transport and hydrodynamic dispersion equations; Annex III: Accuracy and reliability of measurements in hydrogeology; Annex IV: Examples of methods and frequencies of measurements within the monitoring programme; Special definitions.
Subject Classification: 0603 - Nuclear power plants; 1300 - Environment
STI/PUB/678
ISBN: 92-0-323585-X
Publication Date: 2-12-1985
This guide deals primarily with design requirements for instrumentation and control systems important to safety but not part of the protection system (Safety Series No. 50-SG-D3). It gives recommendations on instrumentation and control systems for the prevention or termination of plant transients to avoid, if possible, the actuation of safety systems. Contents: Introduction; Extent of the l&C systems; Design basis; Design requirements; Documentation; Appendix: Single failure criterion for safety-related l&C systems.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/678
ISBN: 92-0-423485-7
Publication Date: 9-9-1985
This guide deals primarily with design requirements for instrumentation and control systems important to safety but not part of the protection system (Safety Series No. 50-SG-D3). It gives recommendations on instrumentation and control systems for the prevention or termination of plant transients to avoid, if possible, the actuation of safety systems. Contents: Introduction; Extent of the l&C systems; Design basis; Design requirements; Documentation; Appendix: Single failure criterion for safety-related l&C systems.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/678
ISBN: 92-0-223085-4
Publication Date: 30-7-1985
This guide deals primarily with design requirements for instrumentation and control systems important to safety but not part of the protection system (Safety Series No. 50-SG-D3). It gives recommendations on instrumentation and control systems for the prevention or termination of plant transients to avoid, if possible, the actuation of safety systems. Contents: Introduction; Extent of the l&C systems; Design basis; Design requirements; Documentation; Appendix: Single failure criterion for safety-related l&C systems.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/682
ISBN: 92-0-223086-2
Publication Date: 20-2-1986
This guide describes the first stage of the siting process for nuclear power plants, the site survey, which involves the study and investigation of a large region to select one or more preferred candidate sites. It deals only with the safety aspects in the site survey, although it is recognized that the review of the safety aspects of sites takes place in a larger context, including questions related to feasibility. Contents: Introduction; Site survey process; Organization of a site survey; Specific safety-related site characteristics; Documentation; Annex I: Elements of site survey methodology; Annex II: Screening and ranking of areas and sites; Annex III: Non-safety considerations.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/682
ISBN: 92-0-323285-0
Publication Date: 19-9-1985
This guide describes the first stage of the siting process for nuclear power plants, the site survey, which involves the study and investigation of a large region to select one or more preferred candidate sites. It deals only with the safety aspects in the site survey, although it is recognized that the review of the safety aspects of sites takes place in a larger context, including questions related to feasibility. Contents: Introduction; Site survey process; Organization of a site survey; Specific safety-related site characteristics; Documentation; Annex I: Elements of site survey methodology; Annex II: Screening and ranking of areas and sites; Annex III: Non-safety considerations.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/682
ISBN: 92-0-423685-X
Publication Date: 29-11-1985
This guide describes the first stage of the siting process for nuclear power plants, the site survey, which involves the study and investigation of a large region to select one or more preferred candidate sites. It deals only with the safety aspects in the site survey, although it is recognized that the review of the safety aspects of sites takes place in a larger context, including questions related to feasibility. Contents: Introduction; Site survey process; Organization of a site survey; Specific safety-related site characteristics; Documentation; Annex I: Elements of site survey methodology; Annex II: Screening and ranking of areas and sites; Annex III: Non-safety considerations.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/685
ISBN: 92-0-423387-7
Publication Date: 17-7-1987
This guide addresses the safety objectives of core management, the tasks which have to be accomplished to meet these objectives and the activities undertaken to perform these tasks. These include the preparation of specifications for procurement, loading, utilizing, unloading and testing of fuel and core components. Maintenance and surveillance requirements, the prediction and monitoring of core conditions to evaluate the nuclear and thermal performance, and further safety aspects are covered. Contents: Introduction; Core management; Handling of unirradiated fuel; Implementation of the fuelling plan; Irradiated fuel storage; Core component handling; Preparation for fuel dispatch; Surveillance related to core management; Administrative and organizational aspects; Records; Annex I: Baseline information relating to core management.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/685
ISBN: 92-0-323286-9
Publication Date: 2-4-1986
This guide addresses the safety objectives of core management, the tasks which have to be accomplished to meet these objectives and the activities undertaken to perform these tasks. These include the preparation of specifications for procurement, loading, utilizing, unloading and testing of fuel and core components. Maintenance and surveillance requirements, the prediction and monitoring of core conditions to evaluate the nuclear and thermal performance, and further safety aspects are covered. Contents: Introduction; Core management; Handling of unirradiated fuel; Implementation of the fuelling plan; Irradiated fuel storage; Core component handling; Preparation for fuel dispatch; Surveillance related to core management; Administrative and organizational aspects; Records; Annex I: Baseline information relating to core management.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/685
ISBN: 92-0-223486-8
Publication Date: 12-6-1986
This guide addresses the safety objectives of core management, the tasks which have to be accomplished to meet these objectives and the activities undertaken to perform these tasks. These include the preparation of specifications for procurement, loading, utilizing, unloading and testing of fuel and core components. Maintenance and surveillance requirements, the prediction and monitoring of core conditions to evaluate the nuclear and thermal performance, and further safety aspects are covered. Contents: Introduction; Core management; Handling of unirradiated fuel; Implementation of the fuelling plan; Irradiated fuel storage; Core component handling; Preparation for fuel dispatch; Surveillance related to core management; Administrative and organizational aspects; Records; Annex I: Baseline information relating to core management.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/685
ISBN: 92-0-123085-0
Publication Date: 23-1-1985
This guide addresses the safety objectives of core management, the tasks which have to be accomplished to meet these objectives and the activities undertaken to perform these tasks. These include the preparation of specifications for procurement, loading, utilizing, unloading and testing of fuel and core components. Maintenance and surveillance requirements, the prediction and monitoring of core conditions to evaluate the nuclear and thermal performance, and further safety aspects are covered. Contents: Introduction; Core management; Handling of unirradiated fuel; Implementation of the fuelling plan; Irradiated fuel storage; Core component handling; Preparation for fuel dispatch; Surveillance related to core management; Administrative and organizational aspects; Records; Annex I: Baseline information relating to core management.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/687
ISBN: 92-0-423188-2
Publication Date: 9-5-1988
This guide provides principles and practical details on the provisions to be made in the design of nuclear power plants to protect site personnel and the general public from ionizing radiation during operational states and accident conditions. The dose limitation systems, including the ALARA principle, are described as the basis for appropriately addressing the radiation protection features in nuclear power plant design. Contents: Introduction; Basic concepts of radiation protection; Radiation protection aspects in design; Sources of radiation during normal operation; Sources of radiation under accident conditions; Protection of site personnel during operational states; Protection of site personnel under accident conditions; Protection of the public under accident conditions; Guidelines for determining radiation dose rates during operational states; Considerations for determining potential doses under accident conditions; Monitoring of radiation during operational states; Monitoring of radiation under accident conditions; Process monitoring for radiological protection; Auxiliary facilities; Annex I. Radioactive releases and exposure limits for members of the public; Annex II. Depressurization accidents in AGR reactors; Annex III. Zoning of nuclear power plants; Annex IV. Methodology for source and flux calculations; Annex V. Statement on the role of quantitative optimization in nuclear power plant radiation protection.
Subject Classification: 0603 - Nuclear power plants; 0609 - Radiation protection
STI/PUB/687
ISBN: 92-0-223387-X
Publication Date: 29-4-1987
This guide provides principles and practical details on the provisions to be made in the design of nuclear power plants to protect site personnel and the general public from ionizing radiation during operational states and accident conditions. The dose limitation systems, including the ALARA principle, are described as the basis for appropriately addressing the radiation protection features in nuclear power plant design. Contents: Introduction; Basic concepts of radiation protection; Radiation protection aspects in design; Sources of radiation during normal operation; Sources of radiation under accident conditions; Protection of site personnel during operational states; Protection of site personnel under accident conditions; Protection of the public under accident conditions; Guidelines for determining radiation dose rates during operational states; Considerations for determining potential doses under accident conditions; Monitoring of radiation during operational states; Monitoring of radiation under accident conditions; Process monitoring for radiological protection; Auxiliary facilities; Annex I. Radioactive releases and exposure limits for members of the public; Annex II. Depressurization accidents in AGR reactors; Annex III. Zoning of nuclear power plants; Annex IV. Methodology for source and flux calculations; Annex V. Statement on the role of quantitative optimization in nuclear power plant radiation protection.
Subject Classification: 0603 - Nuclear power plants; 0609 - Radiation protection
STI/PUB/687
ISBN: 92-0-323686-4
Publication Date: 1-7-1986
This guide provides principles and practical details on the provisions to be made in the design of nuclear power plants to protect site personnel and the general public from ionizing radiation during operational states and accident conditions. The dose limitation systems, including the ALARA principle, are described as the basis for appropriately addressing the radiation protection features in nuclear power plant design. Contents: Introduction; Basic concepts of radiation protection; Radiation protection aspects in design; Sources of radiation during normal operation; Sources of radiation under accident conditions; Protection of site personnel during operational states; Protection of site personnel under accident conditions; Protection of the public under accident conditions; Guidelines for determining radiation dose rates during operational states; Considerations for determining potential doses under accident conditions; Monitoring of radiation during operational states; Monitoring of radiation under accident conditions; Process monitoring for radiological protection; Auxiliary facilities; Annex I. Radioactive releases and exposure limits for members of the public; Annex II. Depressurization accidents in AGR reactors; Annex III. Zoning of nuclear power plants; Annex IV. Methodology for source and flux calculations; Annex V. Statement on the role of quantitative optimization in nuclear power plant radiation protection.
Subject Classification: 0603 - Nuclear power plants; 0609 - Radiation protection
STI/PUB/687
ISBN: 92-0-123585-2
Publication Date: 22-8-1985
This Safety Guide provides principles and practical details on the provisions to be made in the design of nuclear power plants to protect site personnel and the general public from ionizing radiation during operational states and accident conditions. The dose limitation systems, including the ALARA principle, are described as the basis for appropriately addressing the radiation protection features in nuclear power plant design. Contents: Introduction; Basic concepts of radiation protection; Radiation protection aspects in design; Sources of radiation during normal operation; Sources of radiation under accident conditions; Protection of site personnel during operational states; Protection of site personnel under accident conditions; Protection of the public under accident conditions; Guidelines for determining radiation dose rates during operational states; Considerations for determining potential doses under accident conditions; Monitoring of radiation during operational states; Monitoring of radiation under accident conditions; Process monitoring for radiological protection; Auxiliary facilities; Annex I. Radioactive releases and exposure limits for members of the public; Annex II. Depressurization accidents in AGR reactors; Annex III. Zoning of nuclear power plants; Annex IV. Methodology for source and flux calculations; Annex V. Statement on the role of quantitative optimization in nuclear power plant radiation protection.
Subject Classification: 0603 - Nuclear power plants; 0609 - Radiation protection
STI/PUB/688
ISBN: 92-0-123385-X
Publication Date: 21-5-1985
Subject Classification: 0609 - Radiation protection; 1300 - Environment
STI/PUB/689
ISBN: 92-0-041185-1
Publication Date: 19-12-1985
Subject Classification: 0801 - Uranium ore processing
STI/PUB/690
ISBN: 92-0-041085-5
Publication Date: 21-11-1985
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/PUB/691
ISBN: 92-0-523988-7
Publication Date: 27-10-1988
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/691
ISBN: 92-0-323385-7
Publication Date: 24-10-1985
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/691
ISBN: 92-0-423685-X
Publication Date: 5-12-1985
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/691
ISBN: 92-0-223185-0
Publication Date: 3-9-1985
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/691
ISBN: 92-0-123185-7
Publication Date: 28-2-1985
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/692
ISBN: 92-0-123485-6
Publication Date: 30-7-1985
Subject Classification: 0608 - Waste repositories; 0612 - Safety analysis
STI/PUB/693
ISBN: 92-0-423687-6
Publication Date: 17-12-1987
Safety requirements for the design of containment systems are presented in a generic form. The various functions of confinement, isolation, energy management, radionuclide management and combustible gas control as well as the structural and leak integrity are covered. Annexes provide examples for the most common design solutions and other aspects. Contents: Introduction; General design considerations; Design basis for the containment system; Design requirements; Tests and inspection; Quality assurance and documentation; Annex I: Examples of containment system design concepts; Annex II: Containment monitoring instrumentation for early detection of developing deviations from normal operation in light water reactors; Annex III: Illustration of categories of isolation features.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/693
ISBN: 92-0-223287-3
Publication Date: 24-4-1987
Safety requirements for the design of containment systems are presented in a generic form. The various functions of confinement, isolation, energy management, radionuclide management and combustible gas control as well as the structural and leak integrity are covered. Annexes provide examples for the most common design solutions and other aspects. Contents: Introduction; General design considerations; Design basis for the containment system; Design requirements; Tests and inspection; Quality assurance and documentation; Annex I: Examples of containment system design concepts; Annex II: Containment monitoring instrumentation for early detection of developing deviations from normal operation in light water reactors; Annex III: Illustration of categories of isolation features.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/693
ISBN: 92-0-323886-7
Publication Date: 23-12-1986
Safety requirements for the design of containment systems are presented in a generic form. The various functions of confinement, isolation, energy management, radionuclide management and combustible gas control as well as the structural and leak integrity are covered. Annexes provide examples for the most common design solutions and other aspects. Contents: Introduction; General design considerations; Design basis for the containment system; Design requirements; Tests and inspection; Quality assurance and documentation; Annex I: Examples of containment system design concepts; Annex II: Containment monitoring instrumentation for early detection of developing deviations from normal operation in light water reactors; Annex III: Illustration of categories of isolation features.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/693
ISBN: 92-0-123785-5
Publication Date: 25-10-1985
Safety requirements for the design of containment systems are presented in a generic form. The various functions of confinement, isolation, energy management, radionuclide management and combustible gas control as well as the structural and leak integrity are covered. Annexes provide examples for the most common design solutions and other aspects. Contents: Introduction; General design considerations; Design basis for the containment system; Design requirements; Tests and inspection; Quality assurance and documentation; Annex I: Examples of containment system design concepts; Annex II: Containment monitoring instrumentation for early detection of developing deviations from normal operation in light water reactors; Annex III: Illustration of categories of isolation features.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/696
ISBN: 92-0-050085-4
Publication Date: 30-9-1985
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/697
ISBN: 92-0-050186-9
Publication Date: 10-3-1986
Subject Classification: 0703 - Reactor technology
STI/PUB/697
ISBN: 92-0-050086-2
Publication Date: 13-1-1986
Subject Classification: 0703 - Reactor technology
STI/PUB/700
ISBN: 92-0-020086-9
Publication Date: 8-4-1986
Proceedings of a symposium organized in co-operation with the United States Nuclear Regulatory Commission and Battelle Columbus Laboratories, Columbus, Ohio, from 28 October to 1 November 1985. Five topics related to source term evaluation were selected for review and discussion, namely in-vessel release, retention in the primary circuit, ex-vessel release, retention in the containment and release from the plant. Contents: Opening session; In-vessel release; Retention in the primary circuit; Ex-vessel release; Retention in containment; Containment challenges (Panel A); Release from the plant; Regulatory implications (Panel B).
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/701
ISBN: 92-0-020186-5
Publication Date: 22-4-1986
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/702
ISBN: 92-0-159085-7
Publication Date: 28-2-1985
Subject Classification: 0702 - Nuclear power operations
STI/PUB/705
ISBN: 92-0-423287-0
Publication Date: 17-7-1987
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/705
ISBN: 92-0-323386-5
Publication Date: 8-5-1986
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/705
ISBN: 92-0-223386-1
Publication Date: 8-5-1986
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/705
ISBN: 92-0-123685-9
Publication Date: 9-9-1985
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/708
ISBN: 92-0-423288-9
Publication Date: 9-5-1988
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/708
ISBN: 92-0-323786-0
Publication Date: 23-6-1986
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/708
ISBN: 92-0-223586-4
Publication Date: 10-12-1986
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/708
ISBN: 92-0-623085-9
Publication Date: 27-11-1985
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/709
ISBN: 92-0-423487-3
Publication Date: 10-12-1987
The purpose of this publication is to provide guidance for operating organizations and public authorities on planning, organizing and conducting emergency preparedness exercises, preparing exercise scenarious and evaluating exercises, and utilizing their results to improve current emergency plans and preparedness. It also provides guidance for reviewing emergency plans, procedures, equipment and facilities with a view to maintaining a satisfactory level of emergency preparedness. Contents: Introduction; Philosophy of exercises and drills; Practical aspects of preparing and conducting drills and exercises; Scenario development; Evaluating the exercise; Updating and improving emergency preparedness; Trianing aspects.
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/709
ISBN: 92-0-223087-0
Publication Date: 29-4-1987
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/709
ISBN: 92-0-323886-7
Publication Date: 23-12-1986
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/709
ISBN: 92-0-623185-5
Publication Date: 13-12-1985
The purpose of this publication is to provide guidance for operating organizations and public authorities on planning, organizing and conducting emergency preparedness exercises, preparing exercise scenarious and evaluating exercises, and utilizing their results to improve current emergency plans and preparedness. It also provides guidance for reviewing emergency plans, procedures, equipment and facilities with a view to maintaining a satisfactory level of emergency preparedness. Contents: Introduction; Philosophy of exercises and drills; Practical aspects of preparing and conducting drills and exercises; Scenario development; Evaluating the exercise; Updating and improving emergency preparedness; Trianing aspects.
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/710
ISBN: 92-0-123985-8
Publication Date: 27-11-1985
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
STI/PUB/711
ISBN: 92-0-123985-8
Publication Date: 27-11-1985
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/713
ISBN: 92-0-123086-9
Publication Date: 20-2-1986
Subject Classification: 0604 - Research reactors; 0611 - Radioactive waste management
STI/PUB/715
ISBN: 92-0-020286-1
Publication Date: 23-10-1986
Proceedings of a symposium, Hannover, Germany, 37 March 1986. The purpose was to review advances made in the area of siting, design and construction of underground repositories for radioactive wastes and to consider developments of future importance. Forty-nine papers were presented, covering general approaches and regulatory aspects, disposal in shallow ground and rock cavities, disposal in deep geological formations and safety assessments. Contents: Keynote address: Are we ready to construct and operate an underground repository? General approaches and regulatory aspects; Disposal in shallow ground and rock cavities; Disposal in deep formations: Investigations on sites; Disposal in deep formations: Repository designs; Safety assessment; PaneI: Performance and safety assessments and their interactions with field investigations of deep geological repositories; Overview of symposium.
Subject Classification: 0608 - Waste repositories; 0804 - Waste management
STI/PUB/716
ISBN: 92-0-020386-8
Publication Date: 18-11-1986
Subject Classification: 0609 - Radiation protection
STI/PUB/718
ISBN: 92-0-020087-7
Publication Date: 19-1-1987
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/718
ISBN: 92-0-020187-3
Publication Date: 26-2-1987
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/721
ISBN: 92-0-050087-0
Publication Date: 7-5-1987
Subject Classification: 0802 - Fuel fabrication and performance
STI/PUB/726
ISBN: 92-0-023086-5
Publication Date: 29-7-1986
Subject Classification: 0609 - Radiation protection
STI/PUB/727
ISBN: 92-0-423390-7
Publication Date: 28-9-1990
Foundations are the link between plant structures and subsoil. Information on the geology and subsurface characteristics of the site is an input for the design. Without proper adaptation of the design to the subsurface situation, safety may be impaired. This guide addresses the mechanical characteristics of different subsurface materials. Contents: Introduction; Design profiles; Methods of analysis; Discussion of relevant aspects; Programme of investigation; Preliminary foundation work; Monitoring of geotechnical parameters; Quality assurance requirements for programmes of investigation; Appendix A: Site investigation programmes; Appendix B: Subsurface investigation techniques; Appendix C: Laboratory testing methods; Appendix D: Foundation soil improvement techniques; Appendix E: Geotechnical instrumentation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/727
ISBN: 92-0-223090-0
Publication Date: 28-2-1990
Foundations are the link between plant structures and subsoil. Information on the geology and subsurface characteristics of the site is an input for the design. Without proper adaptation of the design to the subsurface situation, safety may be impaired. This guide addresses the mechanical characteristics of different subsurface materials. Contents: Introduction; Design profiles; Methods of analysis; Discussion of relevant aspects; Programme of investigation; Preliminary foundation work; Monitoring of geotechnical parameters; Quality assurance requirements for programmes of investigation; Appendix A: Site investigation programmes; Appendix B: Subsurface investigation techniques; Appendix C: Laboratory testing methods; Appendix D: Foundation soil improvement techniques; Appendix E: Geotechnical instrumentation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/727
ISBN: 92-0-324288-0
Publication Date: 24-1-1989
Foundations are the link between plant structures and subsoil. Information on the geology and subsurface characteristics of the site is an input for the design. Without proper adaptation of the design to the subsurface situation, safety may be impaired. This guide addresses the mechanical characteristics of different subsurface materials. Contents: Introduction; Design profiles; Methods of analysis; Discussion of relevant aspects; Programme of investigation; Preliminary foundation work; Monitoring of geotechnical parameters; Quality assurance requirements for programmes of investigation; Appendix A: Site investigation programmes; Appendix B: Subsurface investigation techniques; Appendix C: Laboratory testing methods; Appendix D: Foundation soil improvement techniques; Appendix E: Geotechnical instrumentation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/727
ISBN: 92-0-124186-0
Publication Date: 20-11-1986
Foundations are the link between plant structures and subsoil. Information on the geology and subsurface characteristics of the site is an input for the design. Without proper adaptation of the design to the subsurface situation, safety may be impaired. This guide addresses the mechanical characteristics of different subsurface materials. Contents: Introduction; Design profiles; Methods of analysis; Discussion of relevant aspects; Programme of investigation; Preliminary foundation work; Monitoring of geotechnical parameters; Quality assurance requirements for programmes of investigation; Appendix A: Site investigation programmes; Appendix B: Subsurface investigation techniques; Appendix C: Laboratory testing methods; Appendix D: Foundation soil improvement techniques; Appendix E: Geotechnical instrumentation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/728
ISBN: 92-0-523690-X
Publication Date: 27-9-1990
Subject Classification: 0609 - Radiation protection; 1300 - Environment
STI/PUB/728
ISBN: 92-0-423089-4
Publication Date: 30-3-1989
Subject Classification: 0609 - Radiation protection; 1300 - Environment
STI/PUB/728
ISBN: 92-0-323387-3
Publication Date: 17-7-1987
Subject Classification: 0609 - Radiation protection; 1300 - Environment
STI/PUB/728
ISBN: 92-0-223587-2
Publication Date: 17-7-1987
This publication is a complete revision of Safety Series No. 45, Principles for Establishing Limits for the Release of Radioactive Materials into the Environment (1978), and its Annex (1982). It is concerned with the subject of limiting releases of radioactive effluents during normal, controlled operations of nuclear installations. It does not deal with releases during accidents where it is only possible to limit exposures by intervention. In practice, a choice must be made between releasing radioactive materials directly from an installation, storing them, treating and disposing of them by some means, or a combination of these methods. Contents: Concepts and quantities; Assessment of individual dose; Assessment of collective dose; Setting release limits; References; Explanation of terms.
Subject Classification: 0609 - Radiation protection; 1300 - Environment
STI/PUB/728
ISBN: 92-0-123486-4
Publication Date: 18-7-1986
This publication is a complete revision of Safety Series No. 45, Principles for Establishing Limits for the Release of Radioactive Materials into the Environment (1978), and its Annex (1982). It is concerned with the subject of limiting releases of radioactive effluents during normal, controlled operations of nuclear installations. It does not deal with releases during accidents where it is only possible to limit exposures by intervention. In practice, a choice must be made between releasing radioactive materials directly from an installation, storing them, treating and disposing of them by some means, or a combination of these methods. Contents: Concepts and quantities; Assessment of individual dose; Assessment of collective dose; Setting release limits; References; Explanation of terms.
Subject Classification: 0609 - Radiation protection; 1300 - Environment
STI/PUB/729
ISBN: 92-0-159086-5
Publication Date: 19-3-1986
Subject Classification: 0702 - Nuclear power operations
STI/PUB/730
ISBN: 92-0-323388-1
Publication Date: 1-6-1988
The basic safety approach of defence in depth and high functional system availability is addressed in this guide. Attention is also paid to the safety implications of operator actions and their consideration in the design. Contents: Introduction; Scope; Safety principles; Safety approach; Design requirements; Safety analysis; Equipment qualification; Quality assurance; Appendix A: Postulated initiating events (PIEs); Annex I: Safety principles used in the development of NUSS documents; Annex II: Typical listings for the compilation of postulated initiating events; Annex III: List of safety functions from IAEA Safety Series No. 50-SG-D1.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/730
ISBN: 92-0-423488-1
Publication Date: 19-9-1988
The basic safety approach of defence in depth and high functional system availability is addressed in this guide. Attention is also paid to the safety implications of operator actions and their consideration in the design. Contents: Introduction; Scope; Safety principles; Safety approach; Design requirements; Safety analysis; Equipment qualification; Quality assurance; Appendix A: Postulated initiating events (PIEs); Annex I: Safety principles used in the development of NUSS documents; Annex II: Typical listings for the compilation of postulated initiating events; Annex III: List of safety functions from IAEA Safety Series No. 50-SG-D1.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/730
ISBN: 92-0-223488-4
Publication Date: 15-7-1988
The basic safety approach of defence in depth and high functional system availability is addressed in this guide. Attention is also paid to the safety implications of operator actions and their consideration in the design. Contents: Introduction; Scope; Safety principles; Safety approach; Design requirements; Safety analysis; Equipment qualification; Quality assurance; Appendix A: Postulated initiating events (PIEs); Annex I: Safety principles used in the development of NUSS documents; Annex II: Typical listings for the compilation of postulated initiating events; Annex III: List of safety functions from IAEA Safety Series No. 50-SG-D1.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/730
ISBN: 92-0-123286-1
Publication Date: 21-5-1986
The basic safety approach of defence in depth and high functional system availability is addressed in this guide. Attention is also paid to the safety implications of operator actions and their consideration in the design. Contents: Introduction; Scope; Safety principles; Safety approach; Design requirements; Safety analysis; Equipment qualification; Quality assurance; Appendix A: Postulated initiating events (PIEs); Annex I: Safety principles used in the development of NUSS documents; Annex II: Typical listings for the compilation of postulated initiating events; Annex III: List of safety functions from IAEA Safety Series No. 50-SG-D1.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/731
ISBN: 92-0-423789-9
Publication Date: 1-6-1989
This guide covers the safety design considerations for various reactor coolant and associated systems for operational states and accident conditions including the selection, sizing and reliability aspects. This includes safety systems such as emergency core cooling, residual heat removal or emergency feedwater systems. The detailed design of particular components, e.g. heat exchangers, pumps and vessels, is not covered. Contents: Introduction; Extent of the reactor coolant and associated systems; General design principles; Detailed design principles; Quality assurance; Annex I: Reactor coolant and associated systems diagrams; Annex II: Main reactor coolant system components; Annex III: Listing of pressure boundary codes and standards used in some Member States.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/731
ISBN: 92-0-323587-6
Publication Date: 10-12-1987
This guide covers the safety design considerations for various reactor coolant and associated systems for operational states and accident conditions including the selection, sizing and reliability aspects. This includes safety systems such as emergency core cooling, residual heat removal or emergency feedwater systems. The detailed design of particular components, e.g. heat exchangers, pumps and vessels, is not covered. Contents: Introduction; Extent of the reactor coolant and associated systems; General design principles; Detailed design principles; Quality assurance; Annex I: Reactor coolant and associated systems diagrams; Annex II: Main reactor coolant system components; Annex III: Listing of pressure boundary codes and standards used in some Member States.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/731
ISBN: 92-0-223887-1
Publication Date: 17-12-1987
This guide covers the safety design considerations for various reactor coolant and associated systems for operational states and accident conditions including the selection, sizing and reliability aspects. This includes safety systems such as emergency core cooling, residual heat removal or emergency feedwater systems. The detailed design of particular components, e.g. heat exchangers, pumps and vessels, is not covered. Contents: Introduction; Extent of the reactor coolant and associated systems; General design principles; Detailed design principles; Quality assurance; Annex I: Reactor coolant and associated systems diagrams; Annex II: Main reactor coolant system components; Annex III: Listing of pressure boundary codes and standards used in some Member States.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/731
ISBN: 92-0-123886-X
Publication Date: 27-10-1986
This guide covers the safety design considerations for various reactor coolant and associated systems for operational states and accident conditions including the selection, sizing and reliability aspects. This includes safety systems such as emergency core cooling, residual heat removal or emergency feedwater systems. The detailed design of particular components, e.g. heat exchangers, pumps and vessels, is not covered. Contents: Introduction; Extent of the reactor coolant and associated systems; General design principles; Detailed design principles; Quality assurance; Annex I: Reactor coolant and associated systems diagrams; Annex II: Main reactor coolant system components; Annex III: Listing of pressure boundary codes and standards used in some Member States.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/732
ISBN: 92-0-323787-9
Publication Date: 4-2-1988
This guide covers the mechanical, chemical, thermal, hydraulic, neutronic and irradiation considerations important to the safe design of a nuclear reactor core. The core features of commonly used reactor types including light and heavy water reactors, as well as gas cooled reactors, are addressed. Contents: Introduction; Safety design principles; Core design requirements; Qualification and testing; Quality assurance in design, manufacture and operation; Annex I: Reactivity coefficients; Annex II: Pellet-cladding interaction; Annex III: Design considerations for core management; Annex IV: Examples of postulated initiating events which can influence the core design.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/732
ISBN: 92-0-424088-1
Publication Date: 17-10-1988
This guide covers the mechanical, chemical, thermal, hydraulic, neutronic and irradiation considerations important to the safe design of a nuclear reactor core. The core features of commonly used reactor types including light and heavy water reactors, as well as gas cooled reactors, are addressed. Contents: Introduction; Safety design principles; Core design requirements; Qualification and testing; Quality assurance in design, manufacture and operation; Annex I: Reactivity coefficients; Annex II: Pellet-cladding interaction; Annex III: Design considerations for core management; Annex IV: Examples of postulated initiating events which can influence the core design.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/732
ISBN: 92-0-223787-5
Publication Date: 19-11-1987
This guide covers the mechanical, chemical, thermal, hydraulic, neutronic and irradiation considerations important to the safe design of a nuclear reactor core. The core features of commonly used reactor types including light and heavy water reactors, as well as gas cooled reactors, are addressed. Contents: Introduction; Safety design principles; Core design requirements; Qualification and testing; Quality assurance in design, manufacture and operation; Annex I: Reactivity coefficients; Annex II: Pellet-cladding interaction; Annex III: Design considerations for core management; Annex IV: Examples of postulated initiating events which can influence the core design.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/732
ISBN: 92-0-124086-4
Publication Date: 5-11-1986
This guide covers the mechanical, chemical, thermal, hydraulic, neutronic and irradiation considerations important to the safe design of a nuclear reactor core. The core features of commonly used reactor types including light and heavy water reactors, as well as gas cooled reactors, are addressed. Contents: Introduction; Safety design principles; Core design requirements; Qualification and testing; Quality assurance in design, manufacture and operation; Annex I: Reactivity coefficients; Annex II: Pellet-cladding interaction; Annex III: Design considerations for core management; Annex IV: Examples of postulated initiating events which can influence the core design.
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/733
ISBN: 92-0-424388-0
Publication Date: 24-1-1989
Under the terms of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, the IAEA is the organization with the responsibility for defining high level radioactive wastes or other high level radioactive matter which is unsuitable for dumping at sea. The IAEA established a provisional Definition and Recommendations in 1972 and a revised version in 1978. The present Safety Series document contains the second revised Definition and Recommendations, which were established in 1985. Contents: Scope; 1. Introduction to the Definition and Recommendations; 2. Definition of high level radioactive waste or other high level radioactive matter unsuitable for dumping at sea; 3. Recommendations required by Annex II of the Convention pertaining to the dumping of radioactive wastes; Annex I. Derivation of the quantitative definition of wastes unsuitable for dumping at sea; Annex II. Comparison with previous Definition and Recommendations; Annex III. Summary of meetings and documentation.
Subject Classification: 0611 - Radioactive waste management; 1100 - Legal matters; 1300 - Environment
STI/PUB/733
ISBN: 92-0-323887-5
Publication Date: 22-1-1988
Under the terms of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, the IAEA is the organization with the responsibility for defining high level radioactive wastes or other high level radioactive matter which is unsuitable for dumping at sea. The IAEA established a provisional Definition and Recommendations in 1972 and a revised version in 1978. The present Safety Series document contains the second revised Definition and Recommendations, which were established in 1985. Contents: Scope; 1. Introduction to the Definition and Recommendations; 2. Definition of high level radioactive waste or other high level radioactive matter unsuitable for dumping at sea; 3. Recommendations required by Annex II of the Convention pertaining to the dumping of radioactive wastes; Annex I. Derivation of the quantitative definition of wastes unsuitable for dumping at sea; Annex II. Comparison with previous Definition and Recommendations; Annex III. Summary of meetings and documentation.
Subject Classification: 0611 - Radioactive waste management; 1100 - Legal matters; 1300 - Environment
STI/PUB/733
ISBN: 92-0-223987-8
Publication Date: 22-1-1988
Under the terms of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, the IAEA is the organization with the responsibility for defining high level radioactive wastes or other high level radioactive matter which is unsuitable for dumping at sea. The IAEA established a provisional Definition and Recommendations in 1972 and a revised version in 1978. The present Safety Series document contains the second revised Definition and Recommendations, which were established in 1985. Contents: Scope; 1. Introduction to the Definition and Recommendations; 2. Definition of high level radioactive waste or other high level radioactive matter unsuitable for dumping at sea; 3. Recommendations required by Annex II of the Convention pertaining to the dumping of radioactive wastes; Annex I. Derivation of the quantitative definition of wastes unsuitable for dumping at sea; Annex II. Comparison with previous Definition and Recommendations; Annex III. Summary of meetings and documentation.
Subject Classification: 0611 - Radioactive waste management; 1100 - Legal matters; 1300 - Environment
STI/PUB/733
ISBN: 92-0-123586-0
Publication Date: 29-8-1986
Under the terms of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, the IAEA is the organization with the responsibility for defining high level radioactive wastes or other high level radioactive matter which is unsuitable for dumping at sea. The IAEA established a provisional Definition and Recommendations in 1972 and a revised version in 1978. The present Safety Series document contains the second revised Definition and Recommendations, which were established in 1985. Contents: Scope; 1. Introduction to the Definition and Recommendations; 2. Definition of high level radioactive waste or other high level radioactive matter unsuitable for dumping at sea; 3. Recommendations required by Annex II of the Convention pertaining to the dumping of radioactive wastes; Annex I. Derivation of the quantitative definition of wastes unsuitable for dumping at sea; Annex II. Comparison with previous Definition and Recommendations; Annex III. Summary of meetings and documentation.
Subject Classification: 0611 - Radioactive waste management; 1100 - Legal matters; 1300 - Environment
STI/PUB/734
ISBN: 92-0-424188-8
Publication Date: 25-10-1988
This guide covers the provisions to be made by the operating organization prior to and during the commissioning and operating phases of a nuclear power plant in order to keep the radiological impact on the environment and the radiation exposure of the general public as low as is reasonably achievable. It discusses the main sources of radioactive wastes and the means available for their minimization, the classification and segregation of these wastes and the waste monitoring programmes on-site. Contents: Introduction; Objectives of the waste management programme; Control of waste production; Waste treatment; Waste storage; Waste transport; Effluent releases and environmental monitoring; Abnormal conditions; Administration and organization; Annex I: Operating procedures; Annex II: Monitoring parameters of waste treatment systems; Annex III: Waste treatment systems.
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/734
ISBN: 92-0-323487-X
Publication Date: 19-11-1987
This guide covers the provisions to be made by the operating organization prior to and during the commissioning and operating phases of a nuclear power plant in order to keep the radiological impact on the environment and the radiation exposure of the general public as low as is reasonably achievable. It discusses the main sources of radioactive wastes and the means available for their minimization, the classification and segregation of these wastes and the waste monitoring programmes on-site. Contents: Introduction; Objectives of the waste management programme; Control of waste production; Waste treatment; Waste storage; Waste transport; Effluent releases and environmental monitoring; Abnormal conditions; Administration and organization; Annex I: Operating procedures; Annex II: Monitoring parameters of waste treatment systems; Annex III: Waste treatment systems.
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/734
ISBN: 92-0-223687-9
Publication Date: 26-11-1987
This guide covers the provisions to be made by the operating organization prior to and during the commissioning and operating phases of a nuclear power plant in order to keep the radiological impact on the environment and the radiation exposure of the general public as low as is reasonably achievable. It discusses the main sources of radioactive wastes and the means available for their minimization, the classification and segregation of these wastes and the waste monitoring programmes on-site. Contents: Introduction; Objectives of the waste management programme; Control of waste production; Waste treatment; Waste storage; Waste transport; Effluent releases and environmental monitoring; Abnormal conditions; Administration and organization; Annex I: Operating procedures; Annex II: Monitoring parameters of waste treatment systems; Annex III: Waste treatment systems.
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/734
ISBN: 92-0-123686-7
Publication Date: 19-9-1986
This guide covers the provisions to be made by the operating organization prior to and during the commissioning and operating phases of a nuclear power plant in order to keep the radiological impact on the environment and the radiation exposure of the general public as low as is reasonably achievable. It discusses the main sources of radioactive wastes and the means available for their minimization, the classification and segregation of these wastes and the waste monitoring programmes on-site. Contents: Introduction; Objectives of the waste management programme; Control of waste production; Waste treatment; Waste storage; Waste transport; Effluent releases and environmental monitoring; Abnormal conditions; Administration and organization; Annex I: Operating procedures; Annex II: Monitoring parameters of waste treatment systems; Annex III: Waste treatment systems.
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/735
ISBN: 92-0-424288-4
Publication Date: 23-1-1989
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/735
ISBN: 92-0-523888-0
Publication Date: 27-10-1988
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/735
ISBN: 92-0-323188-9
Publication Date: 4-2-1988
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/735
ISBN: 92-0-223188-5
Publication Date: 4-2-1988
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/735
ISBN: 92-0-123786-3
Publication Date: 8-10-1986
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/736
ISBN: 92-0-141088-3
Publication Date: 18-2-1987
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/PUB/737
ISBN: 92-0-123087-7
Publication Date: 20-2-1987
Subject Classification: 0601 - Uranium mining and milling; 0609 - Radiation protection
STI/PUB/738
ISBN: 92-0-141187-1
Publication Date: 23-11-1987
Subject Classification: 0801 - Uranium ore processing
STI/PUB/739
ISBN: 92-0-123986-6
Publication Date: 24-10-1986
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/740
ISBN: 92-0-423088-6
Publication Date: 28-4-1988
This report was prepared after the Post-Accident Review Meeting on the Chernobyl Accident, Vienna, 2529 August 1986. A team of Soviet experts who presented a report on the accident at the Chernobyl nuclear power station on 26 April 1986 jointly with INSAG members and other associated experts prepared this agreed report on the accident and formulated recommendations for follow-up actions by the IAEA. Contents: Executive summary; Introduction; 1. The accident at Chernobyl Unit 4; 2. The radionuclide release from the accident; 3. The response at the site; 4. Radiation protection aspects of the accident; 5. Safety issues to be pursued; 6. General observations and provisional conclusions; 7. Recommendations; Annex: RBMK reactors at Chernobyl nuclear power station Units 3 and 4.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/740
ISBN: 92-0-323287-7
Publication Date: 19-6-1987
This report was prepared after the Post-Accident Review Meeting on the Chernobyl Accident, Vienna, 25-29 August 1986. A team of Soviet experts who presented a report on the accident at the Chernobyl nuclear power station on 26 April 1986 jointly with INSAG members and other associated experts prepared this agreed report on the accident and formulated recommendations for follow-up actions by the IAEA. Contents: Executive summary; Introduction; 1. The accident at Chernobyl Unit 4; 2. The radionuclide release from the accident; 3. The response at the site; 4. Radiation protection aspects of the accident; 5. Safety issues to be pursued; 6. General observations and provisional conclusions; 7. Recommendations; Annex: RBMK reactors at Chernobyl nuclear power station Units 3 and 4.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/740
ISBN: 92-0-223487-6
Publication Date: 6-7-1987
This report was prepared after the Post-Accident Review Meeting on the Chernobyl Accident, Vienna, 25-29 August 1986. A team of Soviet experts who presented a report on the accident at the Chernobyl nuclear power station on 26 April 1986 jointly with INSAG members and other associated experts prepared this agreed report on the accident and formulated recommendations for follow-up actions by the IAEA. Contents: Executive summary; Introduction; 1. The accident at Chernobyl Unit 4; 2. The radionuclide release from the accident; 3. The response at the site; 4. Radiation protection aspects of the accident; 5. Safety issues to be pursued; 6. General observations and provisional conclusions; 7. Recommendations; Annex: RBMK reactors at Chernobyl nuclear power station Units 3 and 4.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/740
ISBN: 92-0-123186-5
Publication Date: 2-10-1986
This report was prepared after the Post-Accident Review Meeting on the Chernobyl Accident, Vienna, 2529 August 1986. A team of Soviet experts who presented a report on the accident at the Chernobyl nuclear power station on 26 April 1986 jointly with INSAG members and other associated experts prepared this agreed report on the accident and formulated recommendations for follow-up actions by the IAEA. Contents: Executive summary; Introduction; 1. The accident at Chernobyl Unit 4; 2. The radionuclide release from the accident; 3. The response at the site; 4. Radiation protection aspects of the accident; 5. Safety issues to be pursued; 6. General observations and provisional conclusions; 7. Recommendations; Annex: RBMK reactors at Chernobyl nuclear power station Units 3 and 4.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/742
ISBN: 92-0-323087-4
Publication Date: 12-3-1987
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/742
ISBN: 92-0-423087-8
Publication Date: 12-3-1987
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/742
ISBN: 92-0-223187-7
Publication Date: 12-3-1987
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/742
ISBN: 92-0-123386-8
Publication Date: 12-6-1986
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/743
ISBN: 92-0-123687-5
Publication Date: 9-11-1987
Subject Classification: 0610 - Accident response; 0612 - Safety analysis
STI/PUB/744
ISBN: 92-0-224088-4
Publication Date: 17-10-1988
Subject Classification: 0609 - Radiation protection
STI/PUB/744
ISBN: 92-0-123287-X
Publication Date: 10-4-1987
Subject Classification: 0609 - Radiation protection
STI/PUB/745
ISBN: 92-0-424090-3
Publication Date: 28-11-1990
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/745
ISBN: 92-0-223288-1
Publication Date: 9-2-1988
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/745
ISBN: 92-0-323687-2
Publication Date: 10-12-1987
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/745
ISBN: 92-0-124286-7
Publication Date: 19-12-1986
Subject Classification: 0606 - Transport of radioactive material; 0609 - Radiation protection; 1300 - Environment
STI/PUB/751
ISBN: 92-0-424189-6
Publication Date: 10-1-1990
This publication provides practical support to the guidance contained in IAEA Safety Series No. 72, Principles for Establishing Intervention Levels for the Protection of the Public in the Event of a Nuclear Accident or Radiological Emergency. In the event of a nuclear accident or radiological emergency there is a need to determine the levels of projected dose at which it may be necessary to introduce relevant protective measures. However, more practical quantities are needed for the comparison of measurement results made in environmental materials and in foodstuffs. These derived intervention levels (DlLs) need to be determined for the radionuclides of potential radiological importance. This report gives guidance in elaborating the principles, procedures and methodologies relevant to the evaluation of DILs. Contents: Introduction; Intervention levels and principles underlying their estimation; Procedures for establishing derived intervention levels for exposure due to a single radionuclide and single exposure pathway; Estimation of derived intervention levels and their practical application; Annex 1: Derived intervention levels for selected nuclides and exposure pathways; Annex 2: Definition of symbols used.
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/751
ISBN: 92-0-323288-5
Publication Date: 14-3-1988
This publication provides practical support to the guidance contained in IAEA Safety Series No. 72, Principles for Establishing Intervention Levels for the Protection of the Public in the Event of a Nuclear Accident or Radiological Emergency. In the event of a nuclear accident or radiological emergency there is a need to determine the levels of projected dose at which it may be necessary to introduce relevant protective measures. However, more practical quantities are needed for the comparison of measurement results made in environmental materials and in foodstuffs. These derived intervention levels (DlLs) need to be determined for the radionuclides of potential radiological importance. This report gives guidance in elaborating the principles, procedures and methodologies relevant to the evaluation of DILs. Contents: Introduction; Intervention levels and principles underlying their estimation; Procedures for establishing derived intervention levels for exposure due to a single radionuclide and single exposure pathway; Estimation of derived intervention levels and their practical application; Annex 1: Derived intervention levels for selected nuclides and exposure pathways; Annex 2: Definition of symbols used.
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/751
ISBN: 92-0-223388-8
Publication Date: 14-3-1988
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/751
ISBN: 92-0-124386-3
Publication Date: 18-12-1986
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/753
ISBN: 92-0-123387-6
Publication Date: 26-5-1987
Subject Classification: 0609 - Radiation protection
STI/PUB/754
ISBN: 92-0-131287-3
Publication Date: 25-1-1988
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/754
ISBN: 92-0-131187-7
Publication Date: 18-11-1987
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/755
ISBN: 92-0-159586-7
Publication Date: 30-1-1987
Subject Classification: 0702 - Nuclear power operations
STI/PUB/756
ISBN: 92-0-141188-X
Publication Date: 11-4-1988
Proceedings of a Technical Committee meeting, Jakarta, Indonesia, 1619 December 1985, and one in a series of publications dealing with regional studies being carried out on the uranium geology and resources of the world. It provides a review of the specific exploration techniques that are appropriate for the geological and climatic conditions in Asia. The deposits, promising prospects and exploration activities in Bangladesh, China, the Indian subcontinent, Indonesia, Japan, the Republic of Korea, Malaysia, the Philippines, Sri Lanka and Thailand are described. The proceedings also include the findings of two Working Groups on Uranium Provinces and Criteria for Favourability and on Exploration Techniques. Contents: Review papers on uranium deposits and provinces on regional and national scales; Methods and levels of exploration in the different countries of the region; Working Group reports.
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/PUB/758
ISBN: 92-0-050187-7
Publication Date: 17-9-1987
Subject Classification: 0803 - Spent fuel management; 0804 - Waste management
Safety Aspects of the Ageing and Maintenance of Nuclear Power Plants (Vienna, 29 June - 3 July 1987)
STI/PUB/759
ISBN: 92-0-020088-5
Publication Date: 9-2-1988
Subject Classification: 0603 - Nuclear power plants
STI/PUB/761
ISBN: 92-0-050488-4
Publication Date: 12-9-1988
Subject Classification: 0603 - Nuclear power plants; 0700 - Nuclear power
STI/PUB/761
ISBN: 92-0-050588-0
Publication Date: 14-9-1988
Subject Classification: 0603 - Nuclear power plants; 0700 - Nuclear power
STI/PUB/761
ISBN: 92-0-050388-8
Publication Date: 29-6-1988
Subject Classification: 0603 - Nuclear power plants; 0700 - Nuclear power
STI/PUB/761
ISBN: 92-0-050288-1
Publication Date: 30-5-1988
Subject Classification: 0603 - Nuclear power plants; 0700 - Nuclear power
STI/PUB/761
ISBN: 92-0-050088-9
Publication Date: 28-2-1988
Subject Classification: 0603 - Nuclear power plants; 0700 - Nuclear power
STI/PUB/761
ISBN: 92-0-050188-5
Publication Date: 23-8-1988
Subject Classification: 0603 - Nuclear power plants; 0700 - Nuclear power
STI/PUB/767
ISBN: 92-0-141089-1
Publication Date: 24-4-1989
Proceedings of a Technical Committee meeting, Salamanca, Spain, 29 September to 3 October 1986. Magmatic and metamorphic rocks continue to be important sources of uranium despite the fact that in recent years interest in them has been eclipsed by the discovery of larger, lower cost deposits in other geological environments. However, many developing countries have geological environments consisting of magmatic and metamorphic rocks favouring these types of uranium deposits. Individual deposits can be quite large and economically competitive and constitute worthwhile exploration targets. Contents: General characteristics and genesis of uranium deposits in magmatic and metamorphic rocks in Europe, North America, Asia and Africa; Panel discussions.
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/PUB/768
ISBN: 92-0-423290-0
Publication Date: 28-9-1990
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/768
ISBN: 92-0-324188-4
Publication Date: 20-2-1989
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/768
ISBN: 92-0-224288-7
Publication Date: 8-3-1989
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/768
ISBN: 92-0-123487-2
Publication Date: 19-6-1987
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/769
ISBN: 92-0-423190-4
Publication Date: 26-4-1990
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/769
ISBN: 92-0-223089-7
Publication Date: 25-4-1989
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/769
ISBN: 92-0-324088-8
Publication Date: 19-10-1988
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/769
ISBN: 92-0-123787-1
Publication Date: 30-10-1987
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/770
ISBN: 92-0-323088-2
Publication Date: 2-4-1988
This report presents the views of the IAEA's International Nuclear Safety Advisory Group INSAG on the source term issue for LWRs of existing designs. The report considers the present status of source term research and analysis and their implications. It identifies problems which remain to be resolved and indicates areas where work should be initiated to improve safety. Contents: Introduction; Purpose; Probabilistic safety analysis; General issues; High source term sequences; Early containment failure; Remobilization of fission products; Bypass of containment; Other issues; Reduction of risk and source term through accident prevention, management and mitigation; Conclusions; Bibliography; Appendix: Implications of the source term from the Chernobyl accident.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/770
ISBN: 92-0-423388-5
Publication Date: 22-6-1988
This report presents the views of the IAEAs International Nuclear Safety Advisory Group INSAG on the source term issue for LWRs of existing designs. The report considers the present status of source term research and analysis and their implications. It identifies problems which remain to be resolved and indicates areas where work should be initiated to improve safety. Contents: Introduction; Purpose; Probabilistic safety analysis; General issues; High source term sequences; Early containment failure; Remobilization of fission products; Bypass of containment; Other issues; Reduction of risk and source term through accident prevention, management and mitigation; Conclusions; Bibliography; Appendix: Implications of the source term from the Chernobyl accident.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/770
ISBN: 92-0-223088-9
Publication Date: 4-2-1988
This report presents the views of the IAEA's International Nuclear Safety Advisory Group INSAG on the source term issue for LWRs of existing designs. The report considers the present status of source term research and analysis and their implications. It identifies problems which remain to be resolved and indicates areas where work should be initiated to improve safety. Contents: Introduction; Purpose; Probabilistic safety analysis; General issues; High source term sequences; Early containment failure; Remobilization of fission products; Bypass of containment; Other issues; Reduction of risk and source term through accident prevention, management and mitigation; Conclusions; Bibliography; Appendix: Implications of the source term from the Chernobyl accident.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/770
ISBN: 92-0-123187-3
Publication Date: 18-3-1987
This report presents the views of the IAEAs International Nuclear Safety Advisory Group INSAG on the source term issue for LWRs of existing designs. The report considers the present status of source term research and analysis and their implications. It identifies problems which remain to be resolved and indicates areas where work should be initiated to improve safety. Contents: Introduction; Purpose; Probabilistic safety analysis; General issues; High source term sequences; Early containment failure; Remobilization of fission products; Bypass of containment; Other issues; Reduction of risk and source term through accident prevention, management and mitigation; Conclusions; Bibliography; Appendix: Implications of the source term from the Chernobyl accident.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/771
ISBN: 92-0-123788-X
Publication Date: 1-9-1988
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/772
ISBN: 92-0-423689-2
Publication Date: 4-7-1989
This publication is an update of IAEA Safety Series No. 44, published in 1976, necessitated by a number of developments in the technical and regulatory aspects of the management of wastes resulting from the mining and milling of uranium and thorium ores. It consists of two parts: a Code of Practice (Part I) and a Guide to the Code (Part II). The Code sets forth the requirements for the safe and responsible handling of the wastes, while the Guide presents further guidance in the use of the Code together with some discussion of the technology and concepts involved. Contents: Part 1. Code of Practice: 1. Introduction; 2. Objective; 3. Scope; 4. Definitions; 5. Wastes from the mining and milling of radioactive ores, their radiological impact and control by waste management; 6. Principles of radiological protection; 7. Responsibilities; 8. Design of waste management facilities; 9. Collection, storage and treatment of wastes; 10. Operation of waste management facilities; 11. Decommissioning of mines, mills and waste management facilities; 12. Monitoring, surveillance and maintenance. Part 2. Guide to the Code: 1. Introduction; 2. Objective; 3. Scope; 4. Definitions; 5. Wastes from the mining and milling of radioactive ores, their radiological impact and control by waste management; 6. Principles of radiological protection; 7. Responsibilities; 8. Design of waste management facilities; 9. Collection, storage and treatment of wastes; 10. Operation of waste management facilities; 11. Decommissioning of mines, mills and waste management facilities; 12. Monitoring, surveillance and maintenance; References.
Subject Classification: 0601 - Uranium mining and milling; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/772
ISBN: 92-0-224188-0
Publication Date: 17-1-1989
This publication is an update of IAEA Safety Series No. 44, published in 1976, necessitated by a number of developments in the technical and regulatory aspects of the management of wastes resulting from the mining and milling of uranium and thorium ores. It consists of two parts: a Code of Practice (Part I) and a Guide to the Code (Part II). The Code sets forth the requirements for the safe and responsible handling of the wastes, while the Guide presents further guidance in the use of the Code together with some discussion of the technology and concepts involved. Contents: Part 1. Code of Practice: 1. Introduction; 2. Objective; 3. Scope; 4. Definitions; 5. Wastes from the mining and milling of radioactive ores, their radiological impact and control by waste management; 6. Principles of radiological protection; 7. Responsibilities; 8. Design of waste management facilities; 9. Collection, storage and treatment of wastes; 10. Operation of waste management facilities; 11. Decommissioning of mines, mills and waste management facilities; 12. Monitoring, surveillance and maintenance. Part 2. Guide to the Code: 1. Introduction; 2. Objective; 3. Scope; 4. Definitions; 5. Wastes from the mining and milling of radioactive ores, their radiological impact and control by waste management; 6. Principles of radiological protection; 7. Responsibilities; 8. Design of waste management facilities; 9. Collection, storage and treatment of wastes; 10. Operation of waste management facilities; 11. Decommissioning of mines, mills and waste management facilities; 12. Monitoring, surveillance and maintenance; References.
Subject Classification: 0601 - Uranium mining and milling; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/772
ISBN: 92-0-323488-8
Publication Date: 21-7-1987
This publication is an update of IAEA Safety Series No. 44, published in 1976, necessitated by a number of developments in the technical and regulatory aspects of the management of wastes resulting from the mining and milling of uranium and thorium ores. It consists of two parts: a Code of Practice (Part I) and a Guide to the Code (Part II). The Code sets forth the requirements for the safe and responsible handling of the wastes, while the Guide presents further guidance in the use of the Code together with some discussion of the technology and concepts involved. Contents: Part 1. Code of Practice: 1. Introduction; 2. Objective; 3. Scope; 4. Definitions; 5. Wastes from the mining and milling of radioactive ores, their radiological impact and control by waste management; 6. Principles of radiological protection; 7. Responsibilities; 8. Design of waste management facilities; 9. Collection, storage and treatment of wastes; 10. Operation of waste management facilities; 11. Decommissioning of mines, mills and waste management facilities; 12. Monitoring, surveillance and maintenance. Part 2. Guide to the Code: 1. Introduction; 2. Objective; 3. Scope; 4. Definitions; 5. Wastes from the mining and milling of radioactive ores, their radiological impact and control by waste management; 6. Principles of radiological protection; 7. Responsibilities; 8. Design of waste management facilities; 9. Collection, storage and treatment of wastes; 10. Operation of waste management facilities; 11. Decommissioning of mines, mills and waste management facilities; 12. Monitoring, surveillance and maintenance; References.
Subject Classification: 0601 - Uranium mining and milling; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/772
ISBN: 92-0-123587-9
Publication Date: 5-8-1987
This publication is an update of IAEA Safety Series No. 44, published in 1976, necessitated by a number of developments in the technical and regulatory aspects of the management of wastes resulting from the mining and milling of uranium and thorium ores. It consists of two parts: a Code of Practice (Part I) and a Guide to the Code (Part II). The Code sets forth the requirements for the safe and responsible handling of the wastes, while the Guide presents further guidance in the use of the Code together with some discussion of the technology and concepts involved. Contents: Part 1. Code of Practice: 1. Introduction; 2. Objective; 3. Scope; 4. Definitions; 5. Wastes from the mining and milling of radioactive ores, their radiological impact and control by waste management; 6. Principles of radiological protection; 7. Responsibilities; 8. Design of waste management facilities; 9. Collection, storage and treatment of wastes; 10. Operation of waste management facilities; 11. Decommissioning of mines, mills and waste management facilities; 12. Monitoring, surveillance and maintenance. Part 2. Guide to the Code: 1. Introduction; 2. Objective; 3. Scope; 4. Definitions; 5. Wastes from the mining and milling of radioactive ores, their radiological impact and control by waste management; 6. Principles of radiological protection; 7. Responsibilities; 8. Design of waste management facilities; 9. Collection, storage and treatment of wastes; 10. Operation of waste management facilities; 11. Decommissioning of mines, mills and waste management facilities; 12. Monitoring, surveillance and maintenance; References.
Subject Classification: 0601 - Uranium mining and milling; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/773
ISBN: 92-0-323089-0
Publication Date: 27-4-1989
This safety guide is intended to expand the scope of and complement the available Agency literature in the areas of the transport of radioactive materials and emergency planning and preparedness for radiological emergencies. lt provides detailed guidance on how to respond promptly to a transport accident involving radioactive materials in order to mitigate its consequences. Special attention is given to such problems as how to identify the presence of radioactive materials, their quantity and risk; how to assess the radiological consequences of an accident; and what measures should be taken in order to keep public exposures to a minimum and restore the situation to normal as soon as possible. Contents: Section I. Introduction; Section II. Transport regulations; Section III. Emergency response planning; Section IV. Consequences of transport accidents; Section V. Response to transport accidents; Section Vl. Responsibilities for emergency planning and preparedness; Section VII. Training, exercises and updating; Section VIII. Public information; Appendix I: Markings, labels, placards and documents; Appendix II: Examples of response to transport accidents; Appendix III: Examples of some emergency response guides and procedures; Bibliography.
Subject Classification: 0606 - Transport of radioactive material; 0610 - Accident response
STI/PUB/773
ISBN: 92-0-424089-X
Publication Date: 11-12-1989
Subject Classification: 0606 - Transport of radioactive material; 0610 - Accident response
STI/PUB/773
ISBN: 92-0-223789-1
Publication Date: 31-10-1989
Subject Classification: 0606 - Transport of radioactive material; 0610 - Accident response
STI/PUB/773
ISBN: 92-0-123088-5
Publication Date: 11-2-1988
This safety guide is intended to expand the scope of and complement the available Agency literature in the areas of the transport of radioactive materials and emergency planning and preparedness for radiological emergencies. lt provides detailed guidance on how to respond promptly to a transport accident involving radioactive materials in order to mitigate its consequences. Special attention is given to such problems as how to identify the presence of radioactive materials, their quantity and risk; how to assess the radiological consequences of an accident; and what measures should be taken in order to keep public exposures to a minimum and restore the situation to normal as soon as possible. Contents: Section I. Introduction; Section II. Transport regulations; Section III. Emergency response planning; Section IV. Consequences of transport accidents; Section V. Response to transport accidents; Section Vl. Responsibilities for emergency planning and preparedness; Section VII. Training, exercises and updating; Section VIII. Public information; Appendix I: Markings, labels, placards and documents; Appendix II: Examples of response to transport accidents; Appendix III: Examples of some emergency response guides and procedures; Bibliography.
Subject Classification: 0606 - Transport of radioactive material; 0610 - Accident response
STI/PUB/774
ISBN: 92-0-123689-1
Publication Date: 14-11-1989
Subject Classification: 0608 - Waste repositories; 0614 - Legal and governmental aspects
STI/PUB/775
Publication Date: 9-10-1989
Proceedings of a Technical Committee meeting, Vienna, 912 March 1987. This volume brings together current knowledge on the processes involved in the formation of the various types of uranium deposits and helps to clarify the underlying common factors and principles involved. In addition, it includes reports on studies done on various deposit types in different countries. There are panel discussions on three specific topics: the formation of uranium deposits, the use of metallogenic concepts in uranium exploration, and deposit classification schemes and models.
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/PUB/776
ISBN: 92-0-123589-5
Publication Date: 12-10-1989
Over the past decade there have been significant developments in the techniques and methods of monitoring radon and radon daughters, thoron and thoron daughters, and radioactive dusts encountered in the mining and milling of radioactive ores. The development of new techniques and methods of measurement has received increased attention owing to the fact that the efficient control of radon and its daughters in the mining atmosphere, particularly in underground mines, is a difficult task. Epidemiological studies have clearly demonstrated that the incidence of lung cancers among underground uranium miners, and also among underground non-uranium miners who were exposed to radon and radon daughters in their occupations, is higher than that among the general public. This publication is a revision of IAEA Safety Series No. 43, originally issued in 1976. The revised version has been limited in coverage to radiation monitoring and medical surveillance. Contents: 1. Introduction; 2. Administrative requirements; 3. Main physical properties; 4. Strategies for monitoring programmes; 5. Monitoring methods; 6. Personal monitoring; 7. Health related surveillance; Annex I: The licensing process for uranium exploration in France; Annex II: The licensing process for uranium and thorium minemill facilities in Canada.
Subject Classification: 0601 - Uranium mining and milling; 0609 - Radiation protection
STI/PUB/779
ISBN: 92-0-123089-3
Publication Date: 23-2-1989
Subject Classification: 0601 - Uranium mining and milling; 0609 - Radiation protection; 1300 - Environment
STI/PUB/781
ISBN: 92-0-020588-7
Publication Date: 12-1-1989
Proceedings of a conference organized in co-operation with the Commission of the European Communities and OECD/NEA, Tokyo, 1519 February 1988. The conference demonstrated that the development of computer technologies offered great potential in the design of future control rooms for nuclear power plants with enhanced information processing capabilities. Contents: Opening remarks; Review of status and outlook; Human behaviour in plant operation; Plant personnel training; Operator support; Artificial intelligence and accident management; Process control and human engineering in control rooms; Robots for nuclear power plant inspection and maintenance; Human engineering in controls and control rooms; Transients and accident management; Robotics; Final panel; Closing remarks.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/782
ISBN: 92-0-020188-1
Publication Date: 14-7-1988
Proceedings of a symposium jointly organized with OECD/NEA, Sorrento, Italy, 2125 March 1988. The contents of the pro- ceedings represent a wide spectrum of topics and should provide an understanding of the issue of beyond the design basis accidents, quite frequently called severe accidents. The papers give an overview of different national approaches, with the overall emphasis on preventive, mitigative and accident management measures. The most important outcome of the symposium was a clear awareness of accident management questions which were among the most controversial issues discussed. Contents: (Vol. 1) National positions and practices on severe accidents; Accident initiation and analysis; Non-water-cooled nuclear power reactors.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/782
ISBN: 92-0-020288-8
Publication Date: 14-9-1988
Proceedings of a symposium jointly organized with OECD/NEA, Sorrento, Italy, 2125 March 1988. The contents of the pro- ceedings represent a wide spectrum of topics and should provide an understanding of the issue of beyond the design basis accidents, quite frequently called severe accidents. The papers give an overview of different national approaches, with the overall emphasis on preventive, mitigative and accident management measures. The most important outcome of the symposium was a clear awareness of accident management questions which were among the most controversial issues discussed. Contents: (Vol. 2) Accident research and development; Accident management.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/783
ISBN: 92-0-020488-0
Publication Date: 4-1-1989
Proceedings of a conference, Sydney, Australia, 1822 April 1988. The purpose of the conference was to exchange views on the principles of radiation protection, to highlight issues of current importance, to examine the problems encountered in applying the principles of radiation protection and, where possible, to identify generic solutions. The important topics covered were the interface between nuclear safety and radiation protection, practices exempted from regulatory control, a review of the dosimetry of the Hiroshima and Nagasaki survivors, derived intervention levels and the experience gained from the Chernobyl and Goiânia accidents. An additional feature of the conference was the inclusion of two key discussion sessions on the linear doseresponse relationship and on education and training in radiation protection. Contents: (Vol. 2) Occupational radiation protection; Limitation of radioactive releases; Safe disposal of radioactive wastes; Radiological impact of nuclear facilities; Accident response planning; Accident experiences; Panel 2. Radiation protection education and training; Summary of the Conference and closing remarks.
Subject Classification: 0609 - Radiation protection
STI/PUB/783
ISBN: 92-0-020388-4
Publication Date: 19-9-1988
Proceedings of a conference, Sydney, Australia, 1822 April 1988. The purpose of the conference was to exchange views on the principles of radiation protection, to highlight issues of current importance, to examine the problems encountered in applying the principles of radiation protection and, where possible, to identify generic solutions. The important topics covered were the interface between nuclear safety and radiation protection, practices exempted from regulatory control, a review of the dosimetry of the Hiroshima and Nagasaki survivors, derived intervention levels and the experience gained from the Chernobyl and Goiânia accidents. An additional feature of the conference was the inclusion of two key discussion sessions on the linear doseresponse relationship and on education and training in radiation protection. Contents: (Vol. 1) Opening session; Nuclear safety and radiation protection; Evolution of radiation protection principles; Regulation of radiation protection; Optimization and decision aiding; The doseresponse relationship: Implications for nuclear energy; Panel 1. The doseresponse relationship in practice: Problems and solutions.
Subject Classification: 0609 - Radiation protection
STI/PUB/784
ISBN: 92-0-020089-3
Publication Date: 24-2-1989
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/784
ISBN: 92-0-020189-X
Publication Date: 22-3-1989
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/785
ISBN: 92-0-020289-6
Publication Date: 24-4-1989
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/789
ISBN: 92-0-159088-1
Publication Date: 29-1-1988
Subject Classification: 0702 - Nuclear power operations
STI/PUB/794
ISBN: 92-0-152088-3
Publication Date: 24-10-1988
Subject Classification: 0800 - Nuclear fuel cycle and waste management
STI/PUB/796
ISBN: 92-0-523090-1
Publication Date: 3-10-1990
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/796
ISBN: 92-0-423490-3
Publication Date: 3-7-1990
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/796
ISBN: 92-0-323189-7
Publication Date: 7-4-1989
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/796
ISBN: 92-0-223189-3
Publication Date: 24-4-1989
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/796
ISBN: 92-0-123288-8
Publication Date: 11-8-1988
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/797
ISBN: 92-0-523190-8
Publication Date: 3-10-1990
Subject Classification: 0603 - Nuclear power plants
STI/PUB/797
ISBN: 92-0-423590-X
Publication Date: 3-7-1990
This code recommends how to evaluate the site related factors that are taken into account to ensure that the plantsite combination does not constitute an unacceptable risk. After defining the roles of the applicant and the regulatory body in site selection, evaluation and approval, general criteria are given for selecting proposed sites and assessing their suitability, for determining site related safety requirements and for evaluating the acceptability of a site to accommodate a particular nuclear plant. Contents: Definitions; 1. Introduction; 2. General; 3. Criteria; 4. Evaluation of design basis for external events; 5. Site characteristics influencing the effects of the nuclear power plant on the region.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/797
ISBN: 92-0-323289-3
Publication Date: 7-4-1989
This code recommends how to evaluate the site related factors that are taken into account to ensure that the plant-site combination does not constitute an unacceptable risk. After defining the roles of the applicant and the regulatory body in site selection, evaluation and approval, general criteria are given for selecting proposed sites and assessing their suitability, for determining site related safety requirements and for evaluating the acceptability of a site to accommodate a particular nuclear plant. Contents: Definitions; 1. Introduction; 2. General; 3. Criteria; 4. Evaluation of design basis for external events; 5. Site characteristics influencing the effects of the nuclear power plant on the region.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/797
ISBN: 92-0-223289-X
Publication Date: 24-4-1989
This code recommends how to evaluate the site related factors that are taken into account to ensure that the plant-site combination does not constitute an unacceptable risk. After defining the roles of the applicant and the regulatory body in site selection, evaluation and approval, general criteria are given for selecting proposed sites and assessing their suitability, for determining site related safety requirements and for evaluating the acceptability of a site to accommodate a particular nuclear plant. Contents: Definitions; 1. Introduction; 2. General; 3. Criteria; 4. Evaluation of design basis for external events; 5. Site characteristics influencing the effects of the nuclear power plant on the region.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/797
ISBN: 92-0-123388-4
Publication Date: 11-8-1988
This code recommends how to evaluate the site related factors that are taken into account to ensure that the plantsite combination does not constitute an unacceptable risk. After defining the roles of the applicant and the regulatory body in site selection, evaluation and approval, general criteria are given for selecting proposed sites and assessing their suitability, for determining site related safety requirements and for evaluating the acceptability of a site to accommodate a particular nuclear plant. Contents: Definitions; 1. Introduction; 2. General; 3. Criteria; 4. Evaluation of design basis for external events; 5. Site characteristics influencing the effects of the nuclear power plant on the region.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/798
ISBN: 92-0-523290-4
Publication Date: 3-10-1990
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/798
ISBN: 92-0-423690-6
Publication Date: 3-7-1990
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/798
ISBN: 92-0-323389-X
Publication Date: 7-4-1989
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/798
ISBN: 92-0-223389-6
Publication Date: 24-4-1989
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/798
ISBN: 92-0-123488-0
Publication Date: 11-8-1988
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/799
ISBN: 92-0-523390-0
Publication Date: 3-10-1990
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/799
ISBN: 92-0-423790-2
Publication Date: 3-7-1990
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/799
ISBN: 92-0-323489-6
Publication Date: 7-4-1989
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/799
ISBN: 92-0-223489-2
Publication Date: 24-4-1989
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/799
ISBN: 92-0-123588-7
Publication Date: 11-8-1988
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/800
ISBN: 92-0-523490-7
Publication Date: 3-10-1990
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/800
ISBN: 92-0-423890-9
Publication Date: 3-7-1990
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/800
ISBN: 92-0-323589-2
Publication Date: 7-4-1989
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/800
ISBN: 92-0-223589-9
Publication Date: 24-4-1989
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/800
ISBN: 92-0-123688-3
Publication Date: 11-8-1988
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/801
ISBN: 92-0-323090-4
Publication Date: 7-2-1990
This publication provides guidance for establishing a system for the collection, assessment and distribution of information on unusual events of safety significance in nuclear power plants, on a national and international basis. It also describes the concepts, contents and procedures of the IAEA Incident Reporting System (IAEA-IRS). It is directed to both the utility personnel and the regulatory staff of nuclear power plants. Contents: Introduction; Part I: A national system; Part II: IAEA Incident Reporting System (IAEA-IRS); Appendix I: Unusual event reporting categories; Appendix II: Standard format and contents of IRS reports; Appendix III: Checklist for the preparation of an IRS report; Appendix IV: Classification of lessons learned; Annex I: Coded watchlist; Annex II: Dictionary of codes; Definitions.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/801
ISBN: 92-0-423090-8
Publication Date: 30-3-1990
Subject Classification: 0603 - Nuclear power plants
STI/PUB/801
ISBN: 92-0-223390-X
Publication Date: 5-10-1990
This publication provides guidance for establishing a system for the collection, assessment and distribution of information on unusual events of safety significance in nuclear power plants, on a national and international basis. It also describes the concepts, contents and procedures of the IAEA Incident Reporting System (IAEA-IRS). It is directed to both the utility personnel and the regulatory staff of nuclear power plants. Contents: Introduction; Part I: A national system; Part II: IAEA Incident Reporting System (IAEA-IRS); Appendix I: Unusual event reporting categories; Appendix II: Standard format and contents of IRS reports; Appendix III: Checklist for the preparation of an IRS report; Appendix IV: Classification of lessons learned; Annex I: Coded watchlist; Annex II: Dictionary of codes; Definitions.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/801
ISBN: 92-0-123389-2
Publication Date: 14-4-1989
Subject Classification: 0603 - Nuclear power plants
STI/PUB/802
ISBN: 92-0-223190-7
Publication Date: 8-2-1990
Subject Classification: 0603 - Nuclear power plants
STI/PUB/802
ISBN: 92-0-323789-5
Publication Date: 10-8-1989
Subject Classification: 0603 - Nuclear power plants
STI/PUB/802
ISBN: 92-0-423989-1
Publication Date: 10-8-1989
Subject Classification: 0603 - Nuclear power plants
STI/PUB/802
ISBN: 92-0-123188-1
Publication Date: 15-3-1988
This publication is out of print and superseded by INSAG Series No. 12, "Basic Safety Principles for Nuclear Power Plants, 75-INSAG-3 Rev. 1". (STI/PUB/1082)
Subject Classification: 0603 - Nuclear power plants
STI/PUB/803
ISBN: 92-0-020389-2
Publication Date: 4-7-1989
Proceedings of a symposium, jointly organized by the Federal Republic of Germany, IAEA and OECD/NEA, Munich, 710 November 1988. The overall emphasis was placed on the international aspects of nuclear safety. Contents: Opening session; National regulatory practices and safety standards; National regulatory systems; Implementation of regulatory practices (technical issues); Implementation of regulatory practices (operational aspects); Development and trends in safety standards and practices; International aspects; Implementation of developments in safety standards and practices (Panel I); International harmonization of safety standards and practices Need, possibilities and limitations (Panel II).
Subject Classification: 0603 - Nuclear power plants; 0614 - Legal and governmental aspects
STI/PUB/804
ISBN: 92-0-123189-X
Publication Date: 23-2-1989
The widespread use of radiation sources in medicine, agriculture, industry, research and teaching, in spite of all the precautions taken, may cause accidents which result in injury or death of persons and damage to property. All practical steps to prevent such accidents must be taken and emergency actions planned in advance in order to limit injuries and damage. Emergency plans should be sufficiently broad to cover unforeseen or very improbable accidents as well as those that are considered more likely. Such plans should be established by the users of radioactive materials as well as by local emergency agencies and national competent authorities. Contents: Introduction; Accident analysis and action levels; Protective measures; Planning for an emergency response; Procedures for implementation; Medical aspects; Public information; Training and exercises; Maintaining and updating the emergency plans; Appendix I: Examples of accidents involving radioactive materials; Appendix II: Sample radiography contingency plan; Appendix III: A mobile intervention unit.
Subject Classification: 0605 - Radiation sources and accelerators; 0610 - Accident response
STI/PUB/805
ISBN: 92-0-123988-2
Publication Date: 30-1-1989
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/806
ISBN: 92-0-123090-7
Publication Date: 29-1-1990
The purpose of this publication is to provide practical guidance on the application of the dose limitation system contained in the Basic Safety Standards for Radiation Protection, Safety Series No. 9, to operational situations both in large nuclear installations and in much smaller facilities, with special reference to the principles of optimization. It supersedes Safety Series No. 13. Contents: 1. Introduction; 2. Dose limitation system; 3. Optimization and its practical application to operational radiation protection; 4. Major elements of an effective operational radiation protection programme; Annex I: Review of selected parts of the Basic Safety Standards with special reference to operational radiation protection; Annex II: Optimization of radiation protection; Annex III: Techniques for the systematic appraisal of operational radiation protection programmes.
Subject Classification: 0609 - Radiation protection
STI/PUB/807
ISBN: 92-0-123390-6
Publication Date: 6-4-1990
Subject Classification: 0605 - Radiation sources and accelerators; 0609 - Radiation protection; 0614 - Legal and governmental aspects
STI/PUB/808
ISBN: 92-0-123490-2
Publication Date: 14-3-1990
This publication gives guidance on the radiation protection services that are needed during the operation of a nuclear power plant to achieve acceptable performance in radiation safety and on the optimization process that must be applied to these sevices to comply with the ALARA principle. It presents a broad overview of environmental monitoring, radioactive waste management, emergency planning, the transportation of radioactive material and the analytical services associated with the assessment of internal and external radiation doses. Contents: 1. Introduction; 2. A review of the system of dose limitation for radiation protection; 3. Development of a general operational radiation protection programme; 4. Organization and management; 5. Personnel selection and training; 6. Occupational radiation control; 7. Public radiation control; 8. Review of major factors affecting the optimization of operational radiation protection in a nuclear power plant; Annex I: Practical seven stage framework for the optimization of a complete operational programme; Annex II: Example of a policy statement for radiation protection.
Subject Classification: 0603 - Nuclear power plants; 0609 - Radiation protection
STI/PUB/811
ISBN: 92-0-123289-6
Publication Date: 7-4-1989
Subject Classification: 0609 - Radiation protection; 1300 - Environment
STI/PUB/812
ISBN: 92-0-123889-4
Publication Date: 29-11-1989
In this report the term habitability is used to describe a condition that determines whether or not occupancy by operating or emergency response personnel of a vital area of a nuclear installation during an accident is possible on a continuous or transient basis. Improvements and corrective measures in habitability can be designed into new installations or implemented at existing facilities. The report provides guidance on assessing habitability in existing installations and at the design stage for new plants and suggests actions to improve habitability in the event of an accident. Contents: 1. Introduction; 2. Key elements of a habitability assessment methodology; 3. A generic methodology for habitability assessment; 4. Improvement of habitability; 5. Assessment and improvement of habitability after an accident has occurred; Appendix A: Example of assessing and improving habitability for a radiological type of accident scenario; Appendix B: Example of assessing and improving habitability for a non-radiological type of accident scenario.
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/814
ISBN: 92-0-123489-9
Publication Date: 18-7-1989
Subject Classification: 0610 - Accident response
STI/PUB/815
ISBN: 92-0-329089-3
Publication Date: 24-1-1990
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/815
ISBN: 92-0-429089-7
Publication Date: 28-2-1990
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/815
ISBN: 92-0-229089-X
Publication Date: 24-1-1990
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/815
ISBN: 92-0-129088-8
Publication Date: 16-9-1988
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/816
ISBN: 92-0-159488-7
Publication Date: 14-9-1988
Subject Classification: 0702 - Nuclear power operations
STI/PUB/817
ISBN: 92-0-323689-9
Publication Date: 1-6-1989
The need for a consistent international approach to exclusion and exemption of radiation sources and practices from regulatory control has become increasingly evident, especially for sources which may be transported from one country to another, such as consumer products containing very small amounts of radioactive material. This safety guide represents a first international consensus on the subject of exemption principles. It recommends a procedure which might be followed in implementing the IAEA/NEA(OECD)/ILO/WHO Basic Safety Standards for Radiation Protection. Contents: 1. Introduction; 2. Basic concepts; 3. Definitions of practice and source; 4. Principles for exemption; 5. Application of the principles for exemption to a single practice; 6. Preparation and administration of exemptions; Annex: Examples of definitions of some practices and sources.
Subject Classification: 0609 - Radiation protection; 0611 - Radioactive waste management
STI/PUB/817
ISBN: 92-0-423889-5
Publication Date: 19-7-1989
The need for a consistent international approach to exclusion and exemption of radiation sources and practices from regulatory control has become increasingly evident, especially for sources which may be transported from one country to another, such as consumer products containing very small amounts of radioactive material. This safety guide represents a first international consensus on the subject of exemption principles. It recommends a procedure which might be followed in implementing the IAEA/NEA(OECD)/ILO/WHO Basic Safety Standards for Radiation Protection. Contents: 1. Introduction; 2. Basic concepts; 3. Definitions of practice and source; 4. Principles for exemption; 5. Application of the principles for exemption to a single practice; 6. Preparation and administration of exemptions; Annex: Examples of definitions of some practices and sources.
Subject Classification: 0609 - Radiation protection; 0611 - Radioactive waste management
STI/PUB/817
ISBN: 92-0-223689-5
Publication Date: 28-6-1989
The need for a consistent international approach to exclusion and exemption of radiation sources and practices from regulatory control has become increasingly evident, especially for sources which may be transported from one country to another, such as consumer products containing very small amounts of radioactive material. This safety guide represents a first international consensus on the subject of exemption principles. It recommends a procedure which might be followed in implementing the IAEA/NEA(OECD)/ILO/WHO Basic Safety Standards for Radiation Protection. Contents: 1. Introduction; 2. Basic concepts; 3. Definitions of practice and source; 4. Principles for exemption; 5. Application of the principles for exemption to a single practice; 6. Preparation and administration of exemptions; Annex: Examples of definitions of some practices and sources.
Subject Classification: 0609 - Radiation protection; 0611 - Radioactive waste management
STI/PUB/817
ISBN: 92-0-123888-6
Publication Date: 25-9-1988
The need for a consistent international approach to exclusion and exemption of radiation sources and practices from regulatory control has become increasingly evident, especially for sources which may be transported from one country to another, such as consumer products containing very small amounts of radioactive material. This safety guide represents a first international consensus on the subject of exemption principles. It recommends a procedure which might be followed in implementing the IAEA/NEA(OECD)/ILO/WHO Basic Safety Standards for Radiation Protection. Contents: 1. Introduction; 2. Basic concepts; 3. Definitions of practice and source; 4. Principles for exemption; 5. Application of the principles for exemption to a single practice; 6. Preparation and administration of exemptions; Annex: Examples of definitions of some practices and sources.
Subject Classification: 0609 - Radiation protection; 0611 - Radioactive waste management
STI/PUB/818
ISBN: 92-0-123789-8
Publication Date: 19-11-1989
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/819
ISBN: 92-0-123790-1
Publication Date: 22-10-1990
Subject Classification: 0603 - Nuclear power plants
STI/PUB/824
ISBN: 92-0-020489-9
Publication Date: 31-7-1989
Proceedings of a symposium, Vienna, 27 February to 3 March 1989. Within the last decade there has been considerable development in fire protection and nuclear designers now recognize its importance at all design stages. While the principles of fire protection have been implemented worldwide, problems are still apparent in the description of specific aspects of fire behaviour, material properties, system performance, etc. The symposium provided a forum for the discussion of these and other questions. Contents: Standards and licensing; National fire safety practices; Fire safety by design; Fire fighting and a panel on: How to manage real fires once they occur; Computer fire modelling; Fire safety in fuel cycle facilities; Fire testing of materials; Fire risk assessment; Closing statement.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/826
ISBN: 92-0-020290-X
Publication Date: 19-6-1990
Proceedings of a symposium, Vienna, 610 November 1989. The purpose was to provide a forum for review of actual experience gained and lessons learned from recovery techniques and operations in response to serious accidents at nuclear facilities and accidents associated with radioactive materials, and also to consider the development of emergency planning and preparedness resources. A special feature of the symposium programme was a full session on an accident involving a chemical explosion in a high level waste tank at a plutonium extraction plant in the Southern Urals in the USSR in 1957. Contents: Recovery operations from accidents with radioactive materials; On-site recovery operations (nuclear facilities); Offsite recovery operations (nuclear facilities); The accident in the Southern Urals in 1957; Lessons learned from radiological accidents.
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/834
ISBN: 92-0-123590-9
Publication Date: 9-3-1990
The principles of radiation protection recommended by the International Commission on Radiological Protection for the normal operation of a radiation source constitute a dose limitation system that has three components: namely, the justification of a practice, the optimization of radiation protection and the limitation of individual doses. This report describes how the application of these principles may be extended to unexpected or accidental situations by changing from the dose based system of radiation protection to a unified approach within a probabilistic framework. Contents: Summary; 1. Introduction; 2. Basic principles; 3. Concepts and quantities; 4. Measures of societal risk; 5. Justification; 6. Optimization of potential exposures; 7. Limitation of individual risk; 8. Conclusions.
Subject Classification: 0609 - Radiation protection
STI/PUB/835
ISBN: 92-0-124089-9
Publication Date: 14-11-1989
This safety practice publication provides guidance on the available methods for evaluating the reliability of environmental transfer model predictions. It provides a practical introduction to the subject, and particular emphasis has been given to worked examples in the text. It is Intended to supplement existing IAEA publications on environmental assessment methodology. Although the book addresses the subject of environmental dose assessment, the methods described are of general application and are equally useful in other areas where modelling techniques are applied. Contents: 1. Introduction; 2. General aspects of model reliability evaluation; 3. Practical approaches to the evaluation of model reliability; Appendix I: Statistical equations; Appendix II: Latin hypercube sampling; Appendix III: Examples of parameter uncertainty analyses; Glossary.
Subject Classification: 0612 - Safety analysis; 1300 - Environment
STI/PUB/840
ISBN: 92-0-020390-6
Publication Date: 22-11-1990
Proceedings of a symposium, Munich, 711 May 1990. The expanding application of ionizing radiation in medicine, industry and research calls for vigorous promotion of effective radiation protection efforts, not only to prevent any unsafe practices but also to assess correctly and provide authoritative information on the safety of adopted practices. The purpose of the symposium was to review experience gained in Member States with existing infrastructures for ensuring radiation safety and to discuss how safety standards could most effectively be applied in the national context. Contents: Regulation and licensing; National infrastructures; Education and training; Personnel dosimetry services; Control programmes; Services and special issues; International activities; Panel: The role of the IAEA in strengthening radiation protection infrastructures.
Subject Classification: 0609 - Radiation protection; 0614 - Legal and governmental aspects
STI/PUB/847
ISBN: 92-0-129090-X
Publication Date: 31-5-1990
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/848
ISBN: 92-0-123190-3
Publication Date: 22-1-1990
The guide covers the organizational and procedural aspects of effective maintenance for safe operation of nuclear power plants, but does not provide detailed technical advice on the maintenance of particular items. It gives guidance on preventive and remedial measures necessary to ensure safety. Experience from OSART missions and from the use of the Manual on Maintenance of Systems and Components Important to Safety was used for the revision. The sections on the maintenance programme, administrative control and modifications have been revised and a new section on the feedback of experience has been developed. Contents: Definitions; Note on the interpretation of the text; 1. Introduction; 2. Maintenance programme; 3. Organization and responsibilities for maintenance; 4. Administrative controls; 5. Maintenance facilities; 6. Replacements and repairs; 7. Modifications; 8. Stores; 9. Feedback of experience; 10. Records; Surveillance, review and audit programme; Annex: Administrative aspects of maintenance work.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/849
ISBN: 92-0-123290-X
Publication Date: 5-3-1990
This guide provides guidance and recommendations on surveillance activities to ensure that structures, systems and components important to safety are available to perform their functions in accordance with design intent and assumptions. The section on the surveillance programme, its implementation, and the surveillance frequency and extent have been improved. The safety aspects of special tests and experiments, surveillance activity optimization and early ageing surveillance are emphasized. Contents: Definitions; Introduction; Surveillance programme; Major surveillance requirements; Surveillance frequency and extent; Implementation of the surveillance programme; Administrative aspects; Annex: Examples of parameters, systems, structures and components of different types of reactor plants requiring surveillance.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/851
ISBN: 92-0-159389-9
Publication Date: 20-10-1989
Subject Classification: 0702 - Nuclear power operations
STI/PUB/854
ISBN: 92-0-323190-0
Publication Date: 30-3-1990
This document provides basic guidance on protection of humans and the environment from the hazards associated with deep geological disposal of high level radioactive wastes. It reflects the need for internationally harmonized criteria. It sets out a basic safety philosophy for use in planning such disposals, the main objective being the isolation of the radioactive wastes from the human environment for considerable periods of time. The safety principles contained in this book are generally consistent with the recent recommendations of the International Commission on Radiological Protection (ICRP) and the Nuclear Energy Agency of the OECD (OECD/NEA). Contents: 1. Introduction; 2. Definitions; 3. Safety principles; 4. Technical criteria; 5. Assurance of compliance with the safety objectives; 6. Other considerations.
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
STI/PUB/854
ISBN: 92-0-423990-5
Publication Date: 27-9-1990
This document provides basic guidance on protection of humans and the environment from the hazards associated with deep geological disposal of high level radioactive wastes. It reflects the need for internationally harmonized criteria. It sets out a basic safety philosophy for use in planning such disposals, the main objective being the isolation of the radioactive wastes from the human environment for considerable periods of time. The safety principles contained in this book are generally consistent with the recent recommendations of the International Commission on Radiological Protection (ICRP) and the Nuclear Energy Agency of the OECD (OECD/NEA). Contents: 1. Introduction; 2. Definitions; 3. Safety principles; 4. Technical criteria; 5. Assurance of compliance with the safety objectives; 6. Other considerations.
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
STI/PUB/854
ISBN: 92-0-223290-3
Publication Date: 19-2-1990
This document provides basic guidance on protection of humans and the environment from the hazards associated with deep geological disposal of high level radioactive wastes. It reflects the need for internationally harmonized criteria. It sets out a basic safety philosophy for use in planning such disposals, the main objective being isolation of the radioactive wastes from the human environment for considerable periods of time. The safety principles contained in this book are generally consistent with the recent recommendations of the International Commission on Radiological Protection (ICRP) and the Nuclear Energy Agency of the OECD (OECD/NEA). Contents: 1. Introduction; 2. Definitions; 3. Safety principles; 4. Technical criteria; 5. Assurance of compliance with the safety objectives; 6. Other considerations.
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
STI/PUB/854
ISBN: 92-0-123989-0
Publication Date: 28-11-1989
This document provides basic guidance on protection of humans and the environment from the hazards associated with deep geological disposal of high level radioactive wastes. It reflects the need for internationally harmonized criteria. It sets out a basic safety philosophy for use in planning such disposals, the main objective being the isolation of the radioactive wastes from the human environment for considerable periods of time. The safety principles contained in this book are generally consistent with the recent recommendations of the International Commission on Radiological Protection (ICRP) and the Nuclear Energy Agency of the OECD (OECD/NEA). Contents: 1. Introduction; 2. Definitions; 3. Safety principles; 4. Technical criteria; 5. Assurance of compliance with the safety objectives; 6. Other considerations.
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
STI/PUB/857
ISBN: 92-0-123690-5
Publication Date: 6-9-1990
Subject Classification: 0611 - Radioactive waste management; 0614 - Legal and governmental aspects
STI/PUB/866
ISBN: 92-0-123890-8
Publication Date: 30-11-1990
This publication is an updated version of the 1985 Edition of the Transport Regulations and replaces all previous publications of IAEA Safety Series No. 6. It includes the Supplements 1986 and 1988 to the Regulations and the minor changes adopted by the review Panel meeting in Vienna in July 1989. This edition of the Regulations serves as the basis for regulatory requirements in international modal regulatory documents and will continue to do so until the end of 2001 when the 1996 Edition of the Regulations (TS-R-1 (ST-1, Revised)) will serve as that basis. Contents: Section I. Introduction; Section II. General provisions; Section III. Activity and fissile material limits; Section IV. Preparation, requirements and controls for shipment and for storage in transit; Section V. Requirements for radioactive materials and for packagings and packages; Section VI. Test procedures; Section VII. Approval and administrative requirements; Appendix I: Excerpts from list of United Nations numbers, proper shipping name and description and subsidiary risks; Appendix II: Conversion factors and prefixes.
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/867
ISBN: 92-0-123990-4
Publication Date: 6-12-1990
This publication is an updated version of the Second Edition of the Explanatory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (1985 Edition) and replaces all previous versions of Safety Series No. 7. It includes the changes contained in the Regulations for the Safe Transport of Radioactive Material, 1985 Edition, Supplement 1988, as well as modifications adopted by the Review Panel that was convened in July 1989. It explains the provisions of the Regulations with the aim of helping to promote compliance and public acceptance. Contents: Section I. Introduction; Section II. General provisions; Section III. Activity and fissile material limits; Section IV. Preparation, requirements and controls for shipment and for storage in transit; Section V. Requirements for radioactive materials and for packagings and packages; Section VI. Test procedures; Section VII. Approval and administrative requirements; Appendix I: The Q system for the calculation of A1 and A2 values; Appendix II: Derivation of allowable release rates for type B packages; References.
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/869
ISBN: 92-0-124190-9
Publication Date: 29-11-1990
This publication replaces the previous issue of Safety Series No. 80. It includes the changes to Safety Series No. 80 contained in Supplement 1988 to the Regulations for the Safe Transport of Radioactive Material as well a some modifications adopted by the Review Panel meeting held in Vienna in July 1990. Contents: Schedule 1: Limited quantities of radioactive material in expected packages; Schedule 2: Instruments in articles in expected packages; Schedule 3: Articles manufactured from natural uranium, depleted uranium or natural thorium as excepted packages; Schedule 4: Empty packagings as excepted packages; Schedule 5: Low specific activity material (LSA-1); Schedule 6: Low specific activity material (LSA-II); Schedule 7: Low specific activity material (LSA-III); Schedule 8: Surface contaminated objects (SCO-I and SCO-II); Schedule 9: Material in Type A packages; Schedule 10: Material in Type B(U) packages; Schedule 11: Material in Type B(M) packages; Schedule 12: Fissile material; Schedule 13: Material transported under special arrangement; Annex I: Other provisions relating to Schedules 113; Annex II: Summary of approval and prior notification requirements; Annex III: Transport index limits for freight containers and conveyances.
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/881
ISBN: 92-0-159390-2
Publication Date: 9-11-1990
Subject Classification: 0702 - Nuclear power operations