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-EBP-RBMK-01
Publication Date: 2-8-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-EBP-RBMK-01
Publication Date: 2-8-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-EBP-RBMK-02
Publication Date: 17-1-1996
Subject Classification: 0603 - Nuclear power plants
IAEA-EBP-RBMK-02
Publication Date: 7-9-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-EBP-RBMK-03
Publication Date: 26-1-1996
Subject Classification: 0603 - Nuclear power plants
IAEA-EBP-RBMK-03
Publication Date: 23-11-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-EBP-WWER-01
Publication Date: 23-1-1996
Subject Classification: 0603 - Nuclear power plants
IAEA-EBP-WWER-02
Publication Date: 26-1-1996
Subject Classification: 0603 - Nuclear power plants
IAEA-INIS-23
ISBN: 92-0-100295-5
Publication Date: 24-2-1995
This manual provides information and guidance on how to use the FIBRE (Friendly Inputting of Bibliographic Records) software at INIS input centres to prepare and submit records to be included in the INIS database. The manual also provides information on how to install the software.
Subject Classification: 1200 - International Nuclear Information System
IAEA-NCAL-26
Publication Date: 25-1-1995
Subject Classification: 0606 - Transport of radioactive material
IAEA-NCAL-27
Publication Date: 7-2-1996
Subject Classification: 0606 - Transport of radioactive material
IAEA-PRSM-1
Publication Date: 10-3-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-1
Publication Date: 6-9-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-1
Publication Date: 30-6-1994
Subject Classification: 0103 - Medical physics (including dosimetry); 0609 - Radiation protection
IAEA-PRSM-1
Publication Date: 27-2-1992
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-1 (Rev. 1)
Publication Date: 30-5-1996
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-2
Publication Date: 5-12-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-2
Publication Date: 16-10-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-2
Publication Date: 6-9-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-2
Publication Date: 25-3-1992
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-2 (Rev. 1)
Publication Date: 30-5-1996
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-3
Publication Date: 10-3-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-3
Publication Date: 7-9-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-3
Publication Date: 30-6-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-3
Publication Date: 25-3-1992
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-3 (Rev. 1)
Publication Date: 30-5-1996
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-4
Publication Date: 10-3-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-4
Publication Date: 7-9-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-4
Publication Date: 30-6-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-4
Publication Date: 25-3-1992
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-4 (Rev. 1)
Publication Date: 30-5-1996
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-5
Publication Date: 5-12-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-5
Publication Date: 7-9-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-5
Publication Date: 30-6-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-5
Publication Date: 25-3-1992
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-5 (Rev. 1)
Publication Date: 30-5-1996
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-6
Publication Date: 5-12-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-6
Publication Date: 30-6-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-6
Publication Date: 6-9-1994
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-6
Publication Date: 25-3-1992
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-6 (Rev. 1)
Publication Date: 3-6-1996
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-7
Publication Date: 5-12-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-7
Publication Date: 16-10-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-7
Publication Date: 10-3-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-7
Publication Date: 2-7-1993
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-7 (Rev. 1)
Publication Date: 30-5-1996
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-8
Publication Date: 5-12-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-8
Publication Date: 10-3-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-8
Publication Date: 16-10-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-8
Publication Date: 2-7-1993
Subject Classification: 0609 - Radiation protection
IAEA-PRSM-8 (Rev. 1)
Publication Date: 30-5-1996
Subject Classification: 0609 - Radiation protection
IAEA-PRTM-1
Publication Date: 6-4-1995
Subject Classification: 0609 - Radiation protection
IAEA-PRTM-2
Publication Date: 6-4-1995
Subject Classification: 0609 - Radiation protection
IAEA-RDS-1/11
ISBN: 92-0-159191-8
Publication Date: 17-7-1991
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/12
ISBN: 92-0-102692-7
Publication Date: 21-7-1992
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/13
ISBN: 92-0-102193-3
Publication Date: 29-7-1993
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/14
ISBN: 92-0-102694-3
Publication Date: 8-9-1994
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/15
ISBN: 92-0-104395-3
Publication Date: 13-11-1995
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-1/16
ISBN: 92-0-102896-2
Publication Date: 19-9-1996
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-RDS-2/11
ISBN: 92-0-159091-1
Publication Date: 15-5-1991
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/12
ISBN: 92-0-101592-5
Publication Date: 4-5-1992
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/13
ISBN: 92-0-101593-3
Publication Date: 25-5-1993
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/14
ISBN: 92-0-101794-4
Publication Date: 1-8-1994
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/15
ISBN: 92-0-101795-2
Publication Date: 8-6-1995
Subject Classification: 0700 - Nuclear power
IAEA-RDS-2/16
ISBN: 92-0-101896-7
Publication Date: 29-5-1996
Subject Classification: 0700 - Nuclear power
IAEA-TCS-01/02
Publication Date: 17-2-1995
Subject Classification: 0606 - Transport of radioactive material
IAEA-TCS-01/02
Publication Date: 17-2-1995
Subject Classification: 0606 - Transport of radioactive material
IAEA-TCS-01/02
Publication Date: 12-9-1991
Subject Classification: 0606 - Transport of radioactive material
IAEA-TCS-05 Vol. 1
Publication Date: 23-1-1996
Subject Classification: 0609 - Radiation protection
IAEA-TCS-05 Vol. 2
Publication Date: 23-1-1996
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-525 (Rev. 1)
Publication Date: 11-3-1994
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management
IAEA-TECDOC-581
Publication Date: 22-2-1991
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-582
Publication Date: 1-3-1991
Subject Classification: 0804 - Waste management
IAEA-TECDOC-583
Publication Date: 22-2-1991
Subject Classification: 0401 - Uranium geology, exploration and mining
IAEA-TECDOC-584
Publication Date: 22-2-1991
Subject Classification: 0603 - Nuclear power plants; 0802 - Fuel fabrication and performance
IAEA-TECDOC-586
Publication Date: 1-3-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
Inventory of Radioactive Material Entering the Marine Environment: Sea Disposal of Radioactive Waste
IAEA-TECDOC-588
Publication Date: 28-2-1991
Subject Classification: 0804 - Waste management
IAEA-TECDOC-589
Publication Date: 28-2-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-590
Publication Date: 19-4-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-591
Publication Date: 17-4-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-592
Publication Date: 24-4-1991
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-593
Publication Date: 18-4-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-594
Publication Date: 10-4-1991
Subject Classification: 0900 - Plasma physics and nuclear fusion
IAEA-TECDOC-595
Publication Date: 24-7-1991
Subject Classification: 0401 - Uranium geology, exploration and mining
IAEA-TECDOC-596
Publication Date: 12-4-1991
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-597
Publication Date: 24-5-1991
Subject Classification: 0401 - Uranium geology, exploration and mining
IAEA-TECDOC-599
Publication Date: 6-8-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-600
Publication Date: 21-5-1991
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-603
Publication Date: 5-7-1991
Subject Classification: 0609 - Radiation protection; 0804 - Waste management
IAEA-TECDOC-605
Publication Date: 16-7-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-606
Publication Date: 10-7-1991
Subject Classification: 0605 - Radiation sources and accelerators; 0609 - Radiation protection
IAEA-TECDOC-607
Publication Date: 11-7-1991
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-608
Publication Date: 17-7-1991
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-609
Publication Date: 3-7-1991
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
IAEA-TECDOC-610
Publication Date: 28-8-1991
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-611
Publication Date: 24-5-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-612
Publication Date: 18-7-1991
Subject Classification: 0603 - Nuclear power plants; 0705 - Qualification and training of personnel
IAEA-TECDOC-615
Publication Date: 2-9-1991
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-617
Publication Date: 30-8-1991
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-618
Publication Date: 24-10-1991
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-620
Publication Date: 11-10-1991
Subject Classification: 0605 - Radiation sources and accelerators
IAEA-TECDOC-621
Publication Date: 6-12-1991
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
IAEA-TECDOC-622
Publication Date: 10-12-1991
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-624
Publication Date: 4-9-1991
Subject Classification: 0612 - Safety analysis; 0701 - Nuclear power planning and economics
IAEA-TECDOC-626
Publication Date: 9-2-1996
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-626
Publication Date: 9-2-1996
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-626
Publication Date: 22-2-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-626
Publication Date: 25-9-1991
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-627
Publication Date: 10-12-1991
Subject Classification: 0602 - Fuel fabrication and storage; 0603 - Nuclear power plants
IAEA-TECDOC-629
Publication Date: 10-12-1991
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0804 - Waste management
IAEA-TECDOC-630
Publication Date: 23-10-1991
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
IAEA-TECDOC-631
Publication Date: 9-1-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-632
Publication Date: 16-12-1991
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-635
Publication Date: 9-1-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-636
Publication Date: 10-2-1992
Subject Classification: 0604 - Research reactors; 0612 - Safety analysis
IAEA-TECDOC-637
Publication Date: 29-1-1992
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-638
Publication Date: 10-4-1992
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-640
Publication Date: 13-2-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-644
Publication Date: 7-4-1992
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-645
Publication Date: 13-4-1992
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-646
Publication Date: 12-5-1992
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-647
Publication Date: 15-5-1992
Subject Classification: 0304 - Nuclear analytical techniques; 0609 - Radiation protection; 1300 - Environment
IAEA-TECDOC-648
Publication Date: 22-5-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-650
Publication Date: 3-7-1992
Subject Classification: 0401 - Uranium geology, exploration and mining
IAEA-TECDOC-652
Publication Date: 4-9-1992
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-653
Publication Date: 1-7-1992
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-654
Publication Date: 3-7-1992
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-655
Publication Date: 16-7-1992
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-656
Publication Date: 9-7-1992
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-658
Publication Date: 18-6-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-659
Publication Date: 8-7-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-660
Publication Date: 30-7-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-661
Publication Date: 8-7-1992
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-662
Publication Date: 27-8-1992
Subject Classification: 0606 - Transport of radioactive material
Efficiency in Development and Implementation of Safety Regulations for the Use of Ionizing Radiation
IAEA-TECDOC-663
Publication Date: 16-9-1992
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-664
Publication Date: 16-9-1992
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-665
Publication Date: 18-9-1992
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-666
Publication Date: 3-5-1994
Subject Classification: 0701 - Nuclear power planning and economics; 0703 - Reactor technology
IAEA-TECDOC-666
Publication Date: 16-9-1992
Subject Classification: 0701 - Nuclear power planning and economics; 0703 - Reactor technology
IAEA-TECDOC-667
Publication Date: 16-9-1992
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-667
Publication Date: 23-10-1992
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-667
Publication Date: 16-9-1992
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-668
Publication Date: 12-10-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-669
Publication Date: 2-11-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-670
Publication Date: 23-10-1992
Subject Classification: 0702 - Nuclear power operations; 0703 - Reactor technology
IAEA-TECDOC-671
Publication Date: 23-10-1992
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-672
Publication Date: 23-10-1992
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-673
Publication Date: 23-10-1992
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-675
Publication Date: 3-12-1992
Subject Classification: 0608 - Waste repositories
IAEA-TECDOC-677
Publication Date: 5-1-1993
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-678
Publication Date: 6-1-1993
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-679
Publication Date: 22-12-1992
Subject Classification: 0602 - Fuel fabrication and storage; 0803 - Spent fuel management
IAEA-TECDOC-680
Publication Date: 22-12-1992
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
IAEA-TECDOC-681
Publication Date: 6-1-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-682
Publication Date: 14-1-1993
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-684
Publication Date: 25-1-1993
Subject Classification: 0703 - Reactor technology; 0802 - Fuel fabrication and performance
IAEA-TECDOC-685
Publication Date: 25-1-1993
Subject Classification: 0603 - Nuclear power plants; 0705 - Qualification and training of personnel
IAEA-TECDOC-686
Publication Date: 25-1-1993
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-687
Publication Date: 29-1-1993
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-689
Publication Date: 9-2-1993
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management
IAEA-TECDOC-690
Publication Date: 26-2-1993
Subject Classification: 0701 - Nuclear power planning and economics; 0703 - Reactor technology
IAEA-TECDOC-692
Publication Date: 23-2-1993
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-693
Publication Date: 11-3-1993
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-694
Publication Date: 19-2-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-697
Publication Date: 17-5-1993
Subject Classification: 0803 - Spent fuel management; 0804 - Waste management
IAEA-TECDOC-698
Publication Date: 29-3-1993
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-699
Publication Date: 29-3-1993
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-700
Publication Date: 17-5-1993
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-701
Publication Date: 20-4-1993
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-702
Publication Date: 26-4-1993
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-703
Publication Date: 12-5-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-704
Publication Date: 28-5-1993
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-705
Publication Date: 19-5-1993
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-706
Publication Date: 25-6-1993
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-709
Publication Date: 23-6-1993
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-710
Publication Date: 6-7-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-711
Publication Date: 25-6-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-712
Publication Date: 16-8-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-714
Publication Date: 16-8-1993
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-716
Publication Date: 6-9-1993
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-717
Publication Date: 12-8-1993
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-718
Publication Date: 6-9-1993
Subject Classification: 0610 - Accident response
IAEA-TECDOC-719
Publication Date: 13-10-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-720
Publication Date: 12-10-1993
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-722
Publication Date: 22-12-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-722/R
Publication Date: 14-7-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-723
Publication Date: 22-11-1993
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-724
Publication Date: 22-11-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-725
Publication Date: 28-10-1993
Subject Classification: 0608 - Waste repositories
IAEA-TECDOC-727
Publication Date: 16-12-1993
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-727 (Rev. 1) (Rev.1)
Publication Date: 13-12-1996
Subject Classification: 0612 - Safety analysis
IAEA-TECDOC-729
Publication Date: 16-12-1993
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-730
Publication Date: 7-2-1994
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-731
Publication Date: 25-2-1994
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-732
Publication Date: 11-3-1994
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-733
Publication Date: 28-2-1994
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-735
Publication Date: 15-4-1994
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-737
Publication Date: 11-4-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-738
Publication Date: 17-5-1994
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-739
Publication Date: 3-5-1994
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-740
Publication Date: 4-5-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-741
Publication Date: 13-4-1994
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-742
Publication Date: 12-5-1994
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
IAEA-TECDOC-743
Publication Date: 16-1-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-743
Publication Date: 17-5-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-744
Publication Date: 17-5-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-746
Publication Date: 30-5-1994
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-749
Publication Date: 4-10-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-749
Publication Date: 17-6-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-750
Publication Date: 22-6-1994
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-751
Publication Date: 6-7-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-752
Publication Date: 30-6-1994
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-753
Publication Date: 29-8-1994
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-755
Publication Date: 11-8-1994
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-756
Publication Date: 9-9-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-757
Publication Date: 15-9-1994
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-758
Publication Date: 21-10-1994
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-759
Publication Date: 29-9-1994
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-760
Publication Date: 13-9-1994
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-761
Publication Date: 7-9-1994
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-762
Publication Date: 28-10-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-763
Publication Date: 16-11-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-764
Publication Date: 17-11-1994
Subject Classification: 0803 - Spent fuel management; 0804 - Waste management
IAEA-TECDOC-765
Publication Date: 17-11-1994
Subject Classification: 0804 - Waste management
IAEA-TECDOC-766
Publication Date: 18-11-1994
Subject Classification: 0606 - Transport of radioactive material; 0803 - Spent fuel management
IAEA-TECDOC-767
Publication Date: 17-10-1994
Subject Classification: 0804 - Waste management
IAEA-TECDOC-769
Publication Date: 18-11-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-771
Publication Date: 18-1-1995
Subject Classification: 0602 - Fuel fabrication and storage; 0606 - Transport of radioactive material; 0803 - Spent fuel management
IAEA-TECDOC-773
Publication Date: 28-11-1994
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
IAEA-TECDOC-774
Publication Date: 23-11-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-775
Publication Date: 18-1-1995
Subject Classification: 0804 - Waste management
IAEA-TECDOC-776
Publication Date: 26-1-1995
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-778
Publication Date: 24-11-1994
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-780
Publication Date: 13-2-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-782
Publication Date: 2-5-1995
Subject Classification: 0401 - Uranium geology, exploration and mining
Safety and Environmental Aspects of Partitioning and Transmutation of Actinides and Fission Products
IAEA-TECDOC-783
Publication Date: 8-3-1995
Subject Classification: 0803 - Spent fuel management; 1300 - Environment
IAEA-TECDOC-784
Publication Date: 8-3-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-786
Publication Date: 10-3-1995
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-787
Publication Date: 6-3-1995
Subject Classification: 0804 - Waste management
Preparation of Safety Analysis Reports (SARs) for Near Surface Radioactive Waste Disposal Facilities
IAEA-TECDOC-789
Publication Date: 27-3-1995
Subject Classification: 0804 - Waste management
IAEA-TECDOC-790
Publication Date: 30-3-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-791
Publication Date: 25-4-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-792
Publication Date: 12-4-1995
Subject Classification: 0604 - Research reactors
IAEA-TECDOC-793
Publication Date: 24-4-1995
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-794
Publication Date: 25-5-1995
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-795
Publication Date: 10-5-1995
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-796
Publication Date: 25-4-1995
Subject Classification: 0609 - Radiation protection
IAEA-TECDOC-797
Publication Date: 24-5-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-798
Publication Date: 18-5-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-801
Publication Date: 3-7-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-802
Publication Date: 21-8-1995
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-803
Publication Date: 12-7-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-804
Publication Date: 6-7-1995
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-806
Publication Date: 13-7-1995
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-807
Publication Date: 12-7-1995
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-808
Publication Date: 22-8-1995
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-810
Publication Date: 1-9-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-811
Publication Date: 30-8-1995
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-812
Publication Date: 15-9-1995
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-813
Publication Date: 23-8-1995
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-815
Publication Date: 1-9-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-816
Publication Date: 29-9-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-817
Publication Date: 1-9-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-819
Publication Date: 7-9-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-820
Publication Date: 30-8-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-821
Publication Date: 31-8-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-822
Publication Date: 4-10-1995
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-823
Publication Date: 19-10-1995
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-824
Publication Date: 4-10-1995
Subject Classification: 0401 - Uranium geology, exploration and mining
IAEA-TECDOC-826
Publication Date: 4-10-1995
Subject Classification: 0606 - Transport of radioactive material
IAEA-TECDOC-827
Publication Date: 3-11-1995
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-829
Publication Date: 3-10-1995
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-831
Publication Date: 7-11-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-832
Publication Date: 1-11-1995
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-839
Publication Date: 22-1-1996
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-840
Publication Date: 8-12-1995
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-840/S
Publication Date: 2-11-1995
IAEA-TECDOC-841
Publication Date: 13-11-1995
Subject Classification: 0804 - Waste management
IAEA-TECDOC-842
Publication Date: 8-12-1995
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-844
Publication Date: 8-1-1996
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-846
Publication Date: 23-11-1995
Subject Classification: 0804 - Waste management
IAEA-TECDOC-847
Publication Date: 11-1-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-848
Publication Date: 22-1-1996
Subject Classification: 0603 - Nuclear power plants
IAEA-TECDOC-849
Publication Date: 22-1-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-850
Publication Date: 22-1-1996
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-851
Publication Date: 26-1-1996
Subject Classification: 0804 - Waste management
IAEA-TECDOC-853
Publication Date: 1-12-1995
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-855
Publication Date: 5-2-1996
Subject Classification: 0611 - Radioactive waste management
IAEA-TECDOC-856
Publication Date: 13-2-1996
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
IAEA-TECDOC-858
Publication Date: 11-3-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-861
Publication Date: 6-3-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-862
Publication Date: 23-2-1996
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-863
Publication Date: 12-4-1996
Subject Classification: 0701 - Nuclear power planning and economics
IAEA-TECDOC-864
Publication Date: 6-3-1996
Subject Classification: 0804 - Waste management
IAEA-TECDOC-865
Publication Date: 10-6-1996
Subject Classification: 0804 - Waste management
IAEA-TECDOC-865
Publication Date: 17-4-1996
Subject Classification: 0804 - Waste management
IAEA-TECDOC-865
Publication Date: 25-4-1996
Subject Classification: 0804 - Waste management
IAEA-TECDOC-866
Publication Date: 22-4-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-867
Publication Date: 12-4-1996
Subject Classification: 0610 - Accident response
IAEA-TECDOC-868
Publication Date: 25-4-1996
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-872
Publication Date: 5-6-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-876
Publication Date: 30-4-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-878
Publication Date: 20-5-1996
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-881
Publication Date: 31-5-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-882
Publication Date: 10-6-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-884
Publication Date: 28-6-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-885
Publication Date: 25-7-1996
Subject Classification: 0801 - Uranium ore processing
IAEA-TECDOC-886
Publication Date: 22-7-1996
Subject Classification: 0804 - Waste management
IAEA-TECDOC-887
Publication Date: 27-6-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-892
Publication Date: 12-9-1996
Subject Classification: 1300 - Environment
IAEA-TECDOC-894
Publication Date: 12-9-1996
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-895
Publication Date: 10-9-1996
Subject Classification: 0804 - Waste management
IAEA-TECDOC-898
Publication Date: 3-9-1996
Subject Classification: 0701 - Nuclear power planning and economics; 0703 - Reactor technology
IAEA-TECDOC-899
Publication Date: 12-9-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-900
Publication Date: 12-9-1996
Subject Classification: 0803 - Spent fuel management
IAEA-TECDOC-901
Publication Date: 20-9-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-906
Publication Date: 18-10-1996
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-907
Publication Date: 18-11-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-908
Publication Date: 18-10-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-911
Publication Date: 2-12-1996
Subject Classification: 0804 - Waste management
IAEA-TECDOC-912
Publication Date: 30-10-1996
Subject Classification: 0702 - Nuclear power operations
IAEA-TECDOC-916
Publication Date: 2-12-1996
Subject Classification: 0802 - Fuel fabrication and performance
IAEA-TECDOC-917
Publication Date: 2-12-1996
Subject Classification: 0700 - Nuclear power
IAEA-TECDOC-918
Publication Date: 13-12-1996
Subject Classification: 0800 - Nuclear fuel cycle and waste management; 1300 - Environment
IAEA-TECDOC-920
Publication Date: 16-12-1996
Subject Classification: 0703 - Reactor technology
IAEA-TECDOC-921
Publication Date: 16-12-1996
Subject Classification: 0802 - Fuel fabrication and performance
IAEA/CMS/01
Publication Date: 21-6-1991
Subject Classification: 0603 - Nuclear power plants; 0700 - Nuclear power
IAEA/CMS/04
Publication Date: 20-10-1992
Subject Classification: 0701 - Nuclear power planning and economics
IAEA/CMS/05
Publication Date: 7-1-1993
Subject Classification: 0701 - Nuclear power planning and economics
IAEA/CMS/06
Publication Date: 10-4-1995
Subject Classification: 0603 - Nuclear power plants
IAEA/CMS/07
Publication Date: 22-12-1995
Subject Classification: 0606 - Transport of radioactive material
IAEA/CMS/08 Vol. 1
Publication Date: 29-9-1995
Subject Classification: 0701 - Nuclear power planning and economics
IAEA/CMS/08 Vol. 2
Publication Date: 29-9-1995
Subject Classification: 0701 - Nuclear power planning and economics
IAEA/RSRA/01
Publication Date: 17-10-1995
Subject Classification: 0609 - Radiation protection
IAEA/WMRA/21
Publication Date: 20-1-1993
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/22
Publication Date: 25-8-1995
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/010/240/2
ISBN: 92-0-155191-6
Publication Date: 17-4-1991
This guidebook is a revised version of Technical Reports Series No. 240, published in 1984. It provides a summary of the experience and information in many areas related to spent fuel storage. It will allow a better understanding of the many problems involved and permit countries that are planning for or operating nuclear power reactors to review the issues in a more informative manner. In view of the large quantity of spent fuel discharged from nuclear power plants, long term storage is currently the primary option for the management of spent fuel. The proven wet storage concept is expected to continue to be used in the future. The design and the technological, economic and material problems of safe spent fuel storage will remain a focus of attention, with particular emphasis on dry storage technology, rod consolidation and other advanced concepts. Contents: 1. Introduction; 2. Spent fuel storage technology; 3. Transport of spent fuel; 4. Economics of spent fuel storage; 5. Regulatory, institutional and safety aspects; 6. International safeguards; 7. Factors used in evaluating spent fuel storage options; 8. International co-operation; Annex A: AFR storage facility Clab, Sweden; Annex B: Development of AFR storage design in the USSR; Annex C: Spent fuel storage in the Federal Republic of Germany; Annex D: United States horizontal concrete dry storage system; Annex E: Canadian experience with the dry storage of used CANDU fuel; Annex F: United States dry cask storage experience; Annex G: United States experience with spent fuel rod consolidation; Annex H: Fuel storage ponds at Sellafield, United Kingdom; Annex I: Acronyms and abbreviations; Annex J: Glossary.
Subject Classification: 0803 - Spent fuel management
STI/DOC/010/320
ISBN: 92-0-125091-6
Publication Date: 22-1-1991
The present report provides an appreciation of the types and quantities of spent fuel for disposal and reviews the current state of knowledge of the behaviour of spent fuel under repository conditions. It further contains comments and discussions on technical and safety aspects specific to the disposal of spent fuel, discussed at a Technical Committee meeting held in Vienna in June 1988. Contents: 1. Introduction; 2. Type of spent fuel; 3. Effect of in-reactor operations on fuels; 4. Behaviour of spent fuel in the disposal environment; 5. Safety and environmental assessments of spent fuel as a final waste form; 6. Engineering evaluations and demonstrations of spent fuel disposal; 7. Summary.
Subject Classification: 0803 - Spent fuel management; 0804 - Waste management
STI/DOC/010/321
ISBN: 92-0-125191-2
Publication Date: 23-1-1991
This report provides a comprehensive review of management insights and principles on on-site, post-accident activities at nuclear power plants experiencing significant fuel damage. It combines information on emergency response procedures and off-site plans with a discussion of on-site experience. lt provides a reference text on the requirements that arise after the critical phase of emergency response. Contents: 1. Introduction; 2. Strategic planning; 3. Stabilizing the fuel; 4. Data management and analysis; 5. Initial waste management; 6. Initial decontamination; 7. Fuel removal; 8. Fuel conditioning, transport and interim storage; 9. Abnormal waste; Conditioning to disposal; 10. Preparation for the decommissioning of fuel damaged plants; 11. Conclusions; Annex A: Nuclear Power Plant A-1 (Czechoslovakia) experience.
Subject Classification: 0611 - Radioactive waste management; 0803 - Spent fuel management; 0804 - Waste management
STI/DOC/010/322
ISBN: 92-0-155091-X
Publication Date: 15-4-1991
The guidebook gives a complete survey of non-destructive techniques available for application in the spent fuel pool as well as in hot cells, thereby supplementing an earlier publication, IAEA- TECDOC-245. It provides information on methods of examining water reactor fuel and a basis for further innovations. Contents: 1. Introduction; 2. Defect surveillance and detection; 3. Visual inspection; 4. Dimensional measurements; 5. Oxide layer thickness and crud measurements; 6. Gamma scanning; 7. Neutron radiography and X ray radiography; 8. Fission gas determination; 9. Transfer, collection, documentation and storage of post-irradiation data; 10. Conclusions.
Subject Classification: 0802 - Fuel fabrication and performance
STI/DOC/010/323
ISBN: 92-0-125291-9
Publication Date: 7-6-1991
Subject Classification: 0401 - Uranium geology, exploration and mining; 1300 - Environment
STI/DOC/010/324
ISBN: 92-0-125391-5
Publication Date: 12-6-1991
This publication contains information on the dosimetry and monitoring of tritium, the use of protective clothing for work with tritium, safe practices in tritium handling laboratories and details of tritium compatible materials. The information has been compiled from experience in the various applications of tritium and should represent valuable source material to all users of tritium, including those involved in fusion R&D. Contents: 1. Introduction; 2. Radiological hazards and dosimetry; 3. Tritium monitoring; 4. Personal protective clothing; 5. Properties and compatibility of materials for safe practice in tritium containing systems; 6. Management of tritiated wastes; 7. Safe handling of tritium in laboratories; Annex I: Gaseous tritium light source manufacturing; Annex II: Commercial radiochemical manufacturing; Annex III: Safe handling of tritium in low and medium level university and medical facilities; Annex IV: Tritium safe handling in heavy water reactors.
Subject Classification: 0609 - Radiation protection
STI/DOC/010/325
ISBN: 92-0-125491-1
Publication Date: 6-9-1991
The removal of particulate radioactive material from exhaust air or gases is an essential feature of virtually all nuclear facilities. Recent IAEA publications have covered the broad designs of off-gas and air cleaning systems for a range of nuclear power plants and other facilities. This report is a complementary guidebook that examines in detail the latest developments in the design, operation, maintenance and testing of fibrous air filters. Contents: 1. Introduction; 2. Fundamentals of filtration; 3. Cha-racteristics of filtration systems; 4. Use of aerosol filters in nuclear facilities; 5. Ventilation and filter systems; 6. Handling, inspection and installation of new filter inserts; 7. Filter testing; 8. Handling, storage and disposal of contaminated filter inserts; 9. Trends and developments.
Subject Classification: 0804 - Waste management
STI/DOC/010/326
ISBN: 92-0-125591-8
Publication Date: 1-8-1991
The objective of this report is to present state of the art information on assessments of the complex options available in the management of alpha bearing wastes from the reprocessing of spent fuels and MOX fuel fabrication. Contents: 1. Introduction; 2. Alpha bearing wastes: Types and characteristics; 3. Matrix materials; 4. Immobilization processes; 5. Waste form properties; 6. Packaging the final waste form; 7. Integrated alpha bearing waste conditioning facilities; 8. Conclusions.
Subject Classification: 0804 - Waste management
STI/DOC/010/327
ISBN: 92-0-125691-4
Publication Date: 1-8-1991
This the second of three IAEA publications dealing with the cleanup of large areas contaminated as a result of a nuclear accident. It is mainly a planning and management document, outlining the broad strategic and tactical approach to cleanup, the management structure and other key requirements. The report also shows how the various subplans interface and interact to ensure that cleanup can be performed safely, efficiently and as quickly as possible under adverse conditions. Contents: 1. Introduction; 2. Purpose; 3. Scope; 4. Responsi- bilities for emergency planning and management; 5. Planning and managing the cleanup; 6. Data management; 7. Geographical co-ordinate grid system; 8. Radiological survey plan; 9. Compliance with release criteria; 10. Logistic support; 11. Quality assurance plan; 12. Training and exercises; 13. Updating the preliminary cleanup plan; 14. Radiation protection and safety of workers; 15. Summary; Appendix A: Brief review of cleanup methodology and technology; Appendix B: Examples of data management systems which could be applied to the cleanup of large areas.
Subject Classification: 0610 - Accident response; 0804 - Waste management
STI/DOC/010/328
ISBN: 92-0-155291-2
Publication Date: 23-10-1991
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/DOC/010/330
ISBN: 92-0-100792-2
Publication Date: 8-5-1992
The problem of ground contamination in the case of a severe nuclear accident is one of special concern. This report gives guidance on planning and management of safe transportation and disposal of large volumes of contaminated materials, with the objective of minimizing the consequences of such an accident. It is closely linked to Technical Reports Series No. 300, Cleanup of Large Areas Contaminated as a Result of a Nuclear Accident (1989), and No. 327, Planning for Cleanup of Large Areas Contaminated as a Result of a Nuclear Accident (1991). Contents: 1. Introduction; 2. Purpose; 3. Scope; 4. Waste characteristics and quantities; 5. Treatment of wastes; 6. Scenarios for the transportation and disposal of wastes; 7. Loading and transportation of large volumes of waste; 8. Disposal of large volumes of waste; 9. Disposal of facility operation, closure and surveillance; 10. Review of operational experience; 11. Radiation protection and safety plan; 12. Conclusions; Appendix A: Radiological criteria required to implement the cleanup of large areas after an accident at a nuclear facility; Appendix B: A generic method for estimating costs of waste loading, transportation and disposal; Appendix C: Experience in Canada with the transportation and long term management of radioactively contaminated soils; Appendix D: Experience in the USA with the transportation and disposal of radium contaminated waste; Appendix E: Transportation and disposal of large volumes of contaminated material arising from cleanup after the Chernobyl accident.
Subject Classification: 0610 - Accident response; 0611 - Radioactive waste management; 0804 - Waste management
STI/DOC/010/332
ISBN: 92-0-100992-5
Publication Date: 20-3-1992
Subject Classification: 0609 - Radiation protection; 0612 - Safety analysis; 1300 - Environment
STI/DOC/010/333
ISBN: 92-0-101092-3
Publication Date: 24-6-1992
The present report provides a comprehensive overview of the release, control and monitoring of radon. lt complements Technical Reports Series No. 335, Current Practices for the Management and Confinement of Uranium Mill Tailings, which provides a general account of the siting, design and construction of tailings impoundments. Contents: Notation; 1. Introduction; 2. Purpose and scope; 3. Factors controlling radon releases; 4. Methods for calculating radon releases from uranium tailings piles; 5. Measurement of radon concentration and flux; 6. Conducting a radon monitoring programme; 7. Summary; Annex A: Mathematical development of radon diffusion equations; Annex B: Refined methods of radon flux calculation; References; Glossary.
Subject Classification: 0801 - Uranium ore processing
STI/DOC/010/334
ISBN: 92-0-101192-X
Publication Date: 24-6-1992
The present report was conceived as a technical document in an effort to achieve international consensus on release criteria for the decommissioning of nuclear facilities. It provides an overview of all the factors to be considered in the development, planning and implementation of a monitoring programme to assure regulatory compliance with criteria for unrestricted release of materials, buildings and sites from decommissioning. Contents: 1. Introduction; 2. Purpose and scope; 3. Release criteria; 4. Common practices of unrestricted release; 5. Factors to be considered in determining a monitoring programme; 6. Instruments and methods; 7. Final survey; 8. Quality assurance and documentation; 9. Cost of monitoring for compliance; References; Appendix: Statistical considerations of the critical level and the detection unit.
Subject Classification: 0804 - Waste management
STI/DOC/010/335
ISBN: 92-0-101292-6
Publication Date: 24-6-1992
The present report provides an updated and comprehensive overview of the subject and supersedes Technical Reports Series No. 209, Current Practices and Options for Confinement of Uranium Mill Tailings, published in 1981. The present worldwide production of uranium mill tailings exceeds 20 million tonnes annually. lt is therefore essential that the environmental and health risks from these materials are reduced to an acceptable level. This report highlights new technological developments in this field as well as operational and managerial experience arising from the application of these methods. Contents: 1. Introduction; 2. Scope; 3. Mining and milling uranium ores; 4. Factors in the management of uranium mill tailings; 5. Release of pollutants from uranium mill tailings to the human environment; 6. Environmental considerations in mill process selection; 7. Impoundment siting and design options; 8. Treatment of liquid effluents and monitoring; 9. Stabilization and rehabilitation of impoundments; 10. Application of radiological protection principles; 11. Assessing the long term safety of closeout options; 12. Summary and conclusions; References; Additional bibliographical references; Appendix I: An example of the use of mathematical models to assess the long term safety of mill tailings closeout options; Appendix II: Abbreviated checklist of considerations relevant to the design, construction and closeout of uranium mill tailings impoundments; Glossary.
Subject Classification: 0801 - Uranium ore processing
STI/DOC/010/337
ISBN: 92-0-101992-0
Publication Date: 8-7-1992
The purpose of this report is to provide a review of chemical precipitation processes for the treatment of low and intermediate level aqueous waste. It supersedes Technical Reports Series No. 89, Chemical Treatment of Radioactive Wastes, published in 1968. It provides data on the performance of existing plants and on improved processes that are in an advanced state of development. Contents: 1. Introduction; 2. Waste segregation and characterization; 3. Chemical and adsorptive precipitation and flocculation; 4. Examples of chemical treatment facilities; 5. Process selection; 6. Process equipment; 7. Sludge conditioning; 8. Concluding remarks.
Subject Classification: 0804 - Waste management
STI/DOC/010/338
ISBN: 92-0-102592-0
Publication Date: 30-7-1992
This technical report, one of a series on the management of ageing nuclear power plants, presents methodologies for selecting plant components important to safety whose ageing should be assessed and for performing ageing management studies. Although the report has been developed for the management of ageing of plant components important to safety, the methodology studies are applicable to components important to plant life. Contents: 1. Introduction; 2. Approach to the management of NPP ageing; 3. Selection of NPP components important to safety for ageing management studies; 4. Methodology for ageing management studies; 5. Recommendations for ageing management pilot studies; Appendix I: Examples of ageing related component degradation and failure; Appendix II: Ageing degradation mechanisms and susceptible materials and components; Appendix III: Examples of summary results of ageing management studies from the USNRCs Nuclear Plant Ageing Research Programme; Appendix IV: Examples of condition indicator trending as a basis for mitigating component ageing.
Subject Classification: 0603 - Nuclear power plants
STI/DOC/010/339
ISBN: 92-0-103192-0
Publication Date: 24-10-1992
This report gives an up to date review of high level waste vitrification and storage facilities currently in an advanced stage of implementation. Contents: 1. Introduction; 2. HLLW; 3. Solidification processes; 4. Current vitrification processes; 5. Glass canister handling procedures generally implemented in the vitrification plants; 6. Safety considerations; 7. Summary.
Subject Classification: 0611 - Radioactive waste management
STI/DOC/010/340
ISBN: 92-0-103692-2
Publication Date: 24-11-1992
The competence of the personnel to establish and implement an effective quality assurance programme is essential for attaining and maintaining the safety, reliability and economic performance of a nuclear installation. This manual offers training packages covering quality assurance principles and practices which can be adjusted to suit different levels of management and working personnel and can be adapted to national variables and differing needs in the field of quality assurance. Contents: 1. Introduction; 2. General description; 3. Programmes of classroom training; 4. Lecture syllabuses for classroom training; 5. On the job training; Appendix I: Typical training for inspection and test personnel performing non-destructive examination; Appendix II: Typical training on the operating principles of an LWR power plant.
Subject Classification: 0704 - Quality assurance; 0705 - Qualification and training of personnel
STI/DOC/010/341
ISBN: 92-0-103792-9
Publication Date: 19-1-1993
Subject Classification: 0401 - Uranium geology, exploration and mining
STI/DOC/010/342
ISBN: 92-0-103892-5
Publication Date: 25-11-1992
This report describes the performance of certain types of engineered barriers, e.g. backfills for excavated areas, buffers between the waste container and the host rock, and seals for boreholes, shafts and drifts, in a deep geological repository system for the disposal of high level radioactive wastes. In addition, it provides technical information relevant to their development. Contents: 1. Introduction; 2. Objectives and scope; 3. Performance of the backfill and sealing systems and their evaluation; 4. Repository design concepts; 5. Seal performance functions; 6. Laboratory and field testing; 7. Summary and conclusions.
Subject Classification: 0804 - Waste management
STI/DOC/010/343
Publication Date: 2-12-1992
This report details the results of the Water Reactor Fuel Extended Burnup Study (WREBUS), the first internationally conducted study of its kind. The report assesses the economic effects of burnup extension, evaluates uranium utilization for PWRs and BWRs (e.g. the need for higher enrichments and possible fuel design changes) and considers environmental, safety and licensing implications. The results of the study provide a basis for understanding incentives and indicating directions for future developments in fuel cycle technologies and for introducing improvements in fuel performance and operational strategies. Contents: 1. Introduction; 2. Incentives for extending burnup; 3. Economic evaluation; 4. Technical aspects; 5. Conclusions; Appendix: Description of the fuel cycle cost method used for the US contribution.
Subject Classification: 0802 - Fuel fabrication and performance; 0803 - Spent fuel management
STI/DOC/010/344
Publication Date: 25-11-1992
The present manual is part of the lAEAs programme on guides on uranium resource assessment and supply. Its purpose is to describe methods of making numerical estimates of undiscovered uranium endowment and of the economic potential of the uranium resources. It provides guidance on choosing the method(s) most applicable to a given situation. Contents: 1. Introduction; 2. Geological analogy principles; 3. Control areas; 4. Approaches to estimation of endowment; 5. Probability considerations; 6. Limited information and subjective probability; 7. Deposit density methods; 8. Mineralized rock density methods; 9. Crustal abundance methods; 10. Economic potential evaluation; 11. Criteria for method selection; 12.Utilization of resource estimates; Appendix I: Glossary; Appendix II: Selected control area descriptions and gradetonnage curves; Appendix III: Case studies.
Subject Classification: 0401 - Uranium geology, exploration and mining; 0601 - Uranium mining and milling
STI/DOC/010/345
ISBN: 92-0-104192-6
Publication Date: 26-11-1992
This report describes various national spent fuel conditioning concepts, the current state of technology, the waste package designs so far developed, and the engineering operations required for their manufacture. It supplements IAEA Technical Reports Series No. 320, Evaluation of Spent Fuel as a Final Waste Form. Contents: 1. Introduction; 2. Major factors in the development of conditioning concepts; 3. Waste package design; 4. Preconditioning processes; 5. Conditioning processes; 6. Summary; Appendix: National spent fuel conditioning concepts.
Subject Classification: 0803 - Spent fuel management
STI/DOC/010/346
ISBN: 92-0-104492-5
Publication Date: 2-12-1992
The objective of this report is to provide an overview of factors relevant to the identification of cleanup requirements and to the choice of a decommissioning option for a severely damaged nuclear power plant. It proposes a methodology for the evaluation of various options and the selection of appropriate action in a particular accident situation. Contents: 1. Introduction; 2. Management after a severe reactor accident; 3. Factors relevant to cleanup and decommissioning after a severe accident; 4. Strategy for cleanup; 5. Strategy for decommissioning; 6. Methodology for selection of the preferred decommissioning option; 7. Conclusions and recommendations; Annex A: Review of four accidents.
Subject Classification: 0804 - Waste management
STI/DOC/010/347
ISBN: 92-0-100193-2
Publication Date: 10-2-1993
This report is a survey of coolant technology in water cooled reactors which focuses on the following objectives: (a) man-sievert reduction; (b) plant life extension; (c) fuel life extension; (d) general safety and materials reliability. Contents: 1. Introduction; 2. Description of reactor coolant systems; 3. Chemistry of primary coolant in water cooled reactors; 4. Corrosion in the primary coolant systems of water cooled reactors; 5. Activity transport mechanisms of water cooled reactors; 6. Decontamination of water cooled reactors; 7. Areas for future research and development; 8. Conclusions.
Subject Classification: 0703 - Reactor technology
STI/DOC/010/348
ISBN: 92-0-100293-9
Publication Date: 25-1-1993
Subject Classification: 0804 - Waste management
STI/DOC/010/349
ISBN: 92-0-100393-5
Publication Date: 27-1-1993
The purpose of this report is to provide an overview of the current knowledge in the field of radioactive waste disposal, limiting itself to the essential topics in this field. It covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and provides basic information on performance assessment methods. Contents: 1. Introduction; 2. Background information; 3. Nature and function of natural barriers; 4. Engineering barriers; 5. Siting and site characterization; 6. Repository concepts and operation; 7. Performance assessment of disposal systems; 8. Regulatory and institutional aspects; 9. Conclusion.
Subject Classification: 0804 - Waste management
STI/DOC/010/350
ISBN: 92-0-100493-1
Publication Date: 25-1-1993
This report provides an explanation of the chemistry of cementation systems and assistance in facilitating the choice of solidification agents and processing equipment. It reviews recent developments in cementation technology for improving the quality of cemented waste forms and gives a brief description of the various cement solidification processes in use. Contents: 1. Introduction; 2. Waste characterization; 3. Characterization of cement for solidification of waste; 4. Cement admixtures; 5. Chemical aspects of waste cementation; 6. Cement solidification processes; 7. Properties of immobilized waste forms.
Subject Classification: 0804 - Waste management
STI/DOC/010/351
ISBN: 92-0-100693-4
Publication Date: 18-3-1993
This report provides guidance on the proper planning and management for the decommissioning of research reactors and other small nuclear facilities. The information contained in the report can, to a large extent, also be applied to the decommissioning of large facilities. Contents: 1. Introduction; 2. Scope of the report; 3. Reasons for and stages of decommissioning; 4. Decommissioning planning; 5. Decommissioning management; 6. Quality assurance; 7. Waste management; 8. Decommissioning cost and financing; 9. Responsibilities and functions of parties in decommissioning; 10. Regulatory interfaces; 11. Recommendations for further work; 12. Summary; Annex: Stages of Decommissioning; Glossary.
Subject Classification: 0804 - Waste management
STI/DOC/010/352
ISBN: 92-0-100793-0
Publication Date: 19-3-1993
The aim of this report is to review and evaluate the accumulated experience in the use of bituminization techniques for the immobilization of radioactive wastes, including the description of incidents which have happened at bituminization facilities, and to give an assessment on the role of bituminization processes in the strategy for radioactive waste management. Contents: 1. Introduction; 2. Characterization of bitumens used for waste immobilization; 3. Types of radioactive wastes suitable for immobilization in bitumen; 4. Immobilization processes: Operational and safety aspects; 5. Properties of bituminized waste forms; 6. Conclusions; Annex: Application of bituminization processes in some Member States.
Subject Classification: 0804 - Waste management
STI/DOC/010/353
ISBN: 92-0-100993-3
Publication Date: 6-4-1993
This report outlines the general characteristics of financing a nuclear power project and presents innovative approaches for power generation financing. It discusses the special conditions and requirements of nuclear power projects and their financing complexities. The availability of adequate and secure financial resources is one of the most crucial constraints in the implementation of nuclear power projects in developing countries. Possible ways and means of dealing with these constraints are presented. Contents: Chapter 1. Introduction; Chapter 2. The status of nuclear power and special circumstances related to the financing of nuclear power projects; Chapter 3. Costs and economic feasibility of nuclear power plants; Chapter 4. Conventional approaches for financing power generation projects in developing countries; Chapter 5. Experience gained and lessons learned; Chapter 6. Alternative approaches for mobilizing financial resources; Chapter 7. Conclusions; References; Glossary; Annex I: Issues affecting the financing of nuclear power plants and the actions proposed for various actors; Annex II: Alternative Energy fund of Egypt; Annex III: Sector understanding on export credits for nuclear power plants; Annex IV: Aliaga thermal power project in Turkey; Annex V: BOT project development cycle.
Subject Classification: 0701 - Nuclear power planning and economics
STI/DOC/010/354
ISBN: 92-0-101493-7
Publication Date: 23-4-1993
The present report consists of two parts. The first and larger part (Sections 14) provides an overview of reactivity accidents: how they can arise, the basic principles of the defence against them, methods of analysis and acceptance criteria. The second part summarizes more recent work on beyond-design-basis reactivity accidents. Contents: 1. Background and overview; 2. Design basis accidents; 3. Experiments on fuel behaviour; 4. Methods for analysing design basis accidents; 5. Beyond-design-basis accidents; 6. Conclusions.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/DOC/010/355
ISBN: 92-0-101993-9
Publication Date: 15-7-1993
This report aims to review the main requirements for waste containers and to provide advice on the design, fabrication, qualification tests and handling of the different types of containers used in the management of low and intermediate level solid radioactive wastes. It contains the requirements that have to be met in the container design in order to comply with the waste package acceptance requirements established by the regulatory authorities for the handling, storage, transport and disposal of radioactive waste. It further highlights the importance of international standardization for waste container requirements, which would facilitate the use of common handling systems and allow operating experience and performance data to be readily interchangeable. Contents: 1. Introduction; 2. Role of the container in waste management; 3. Container design requirements; 4. Materials for containers; 5. Cost considerations; 6. Quality assurance and control; 7. Qualification tests; 8. Conclusions and recommendations; Appendix I: Examples of containers; Appendix II: Corrosion assessments of metallic containers; Appendix III: Specification of a test for thermal cycling resistance in France; Appendix IV: A qualification procedure for fibre reinforced concrete containers in France.
Subject Classification: 0608 - Waste repositories; 0804 - Waste management
STI/DOC/010/356
ISBN: 92-0-102093-7
Publication Date: 7-9-1993
This is the first report reviewing some of the aspects of the recovery and utilization of caesium and strontium from high level waste and the consequent impacts on high level waste management strategy. Contents: 1. Introduction; 2. Current and future arisings of 137Cs and 90Sr from spent nuclear fuel; 3. Potential applications for 137Cs and 90Sr; 4. Impact of fission product separation on high level waste management; 5. Methods for recovery and immobilization of 137Cs and 90Sr; 6. Economic aspects; 7. Public acceptability of radiation sources; 8. Conclusions; Appendix: Some aspects of solvent extraction methods for caesium and strontium recovery from HLW.
Subject Classification: 0803 - Spent fuel management; 0804 - Waste management
STI/DOC/010/358
ISBN: 92-0-102993-4
Publication Date: 2-12-1993
Air cleaning systems are subjected to major challenges under accident conditions and the potential large source terms require the highest environmental protection from atmospheric release. The objective of this report is to consider the principles involved and to survey existing systems and equipment for the mitigation of the consequences of abnormal plant operations, including severe accidents beyond the design basis. Some experiences under abnormal conditions and international trends in the development of accident air cleaning are also included. Contents: 1. Introduction; 2. Source terms; 3. Design principles; 4. Control of airborne contamination in design basis accidents; 5. Control of airborne contamination in severe accidents; 6. Experience and trends; 7. Conclusions and recommendations; Appendix: Testing of off-gas cleaning equipment for nuclear power plants.
Subject Classification: 0703 - Reactor technology; 0804 - Waste management
STI/DOC/010/359
ISBN: 92-0-103593-4
Publication Date: 16-2-1994
The purpose of this publication is to update and expand the first edition, which was published in 1983, and to report on later advances in uranium ore processing. It includes background information about the principles of the unit operations used in uranium ore processing and summarizes the current state of the art. Extensive references provide sources for specific technological details. Contents: Introduction; Part I. Uranium resources and mining technology; Chapter 1. Uranium resources; Chapter 2. Mining technology; Part II. Processing technology; Chapter 3. Processing concepts; Chapter 4. Ore preparation; Chapter 5. Leaching; Chapter 6. Solidliquid separation; Chapter 7. Solution purification; Chapter 8. Product recovery; Chapter 9. By-products; Part III. Waste management and the environment; Chapter 10. Tailings management technology; Part IV. Flow sheet examples; Chapter 11. Olympic Dam; Chapter 12. Key Lake; Chapter 13. Rabbit Lake; Chapter 14. Lodève; Chapter 15. Rossing; Chapter 16. Cominak; Chapter 17. White Mesa; Chapter 18. Rosita (in situ leaching).
Subject Classification: 0401 - Uranium geology, exploration and mining; 0801 - Uranium ore processing
STI/DOC/010/360
ISBN: 92-0-100494-X
Publication Date: 18-5-1994
This report describes all existing methods of treatment of solid, low and intermediate level radioactive waste: mechanical, thermal, melting, chemical, biological and photochemical processes; both established proven technologies and advanced methods. It further discusses the treatment of generated liquid, solid and gaseous secondary waste. Comprehensive references on the subject are also given. Contents: 1. Introduction; 2. Waste treatment objectives and strategies; 3. Sources and types of waste; 4. Pretreatment of solid radioactive waste; 5. Mechanical treatment; 6. Thermal treatment processes; 7. Melting and sintering processes; 8. Chemical, biological and photochemical treatment processes; 9. Decontamination of equipment and components; 10. Conditioning of processed primary wastes; 11. Secondary waste treatment.
Subject Classification: 0804 - Waste management
STI/DOC/010/361
ISBN: 92-0-100594-6
Publication Date: 17-10-1994
This report provides a methodology for calculating the costs of different options for interim storage of spent fuel produced in reactor cores. It considers different technical features and storage options and defines the factors affecting all options. The report further analyses the major cost categories, calculates the net present value of each option and determines the levelized cost. It also includes a sensitivity analysis, taking into account the uncertainty of the different cost estimates. Contents: 1. Introduction; 2. Spent fuel management; 3. Tech-nical features of spent fuel storage; 4. Storage options and cost considerations; 5. Cost considerations; 6. Method of cost analysis; 7. Cost analysis; 8. Financing the options; Appendix I: AR storage enhancement: Reracking with compact storage racks in Germany; Appendix II: A stand alone AR storage facility: The TVO-KPA pool storage facility at Olkiluoto in Finland; Appendix III: An AFR storage facility: The CLAB pool storage facility at Oskarshamn in Sweden; Appendix IV: An AFR storage facility: Pool storage facilites at the Cogéma processing plant at La Hague in France; Appendix V: An AFR storage facility: The dry cask storage facility at Gorleben in Germany.
Subject Classification: 0803 - Spent fuel management
STI/DOC/010/362
ISBN: 92-0-100694-2
Publication Date: 26-9-1994
The purpose of this report is to provide an overview of the factors involved and assistance in planning and implementing the decommissioning of mining and milling facilities and the closeout of mines, tailings piles, mining debris and leach residues. Restoration of the site, vicinity properties and groundwater is also part of the report. Contents: 1. Introduction; 2. Purpose; 3. Scope; 4. Objectives of decommissioning/closeout programmes; 5. Regulatory control for decommissioning/closeout; 6. Site characterization; 7. Plan-ning and technical considerations; 8. Implementation of the decommissioning/closeout plan; 9. Radiation protection, health and safety programmes during decommissioning/closeout activities; 10. Post-closeout monitoring and surveillance programmes; 11. Cost estimating and financing for decommissioning/closeout; 12. Documentation for decommissioning/closeout; 13. QA programme for decommissioning/closeout; 14. Summary and conclusions; Annex I: Examples of national regulatory requirements, regulations and criteria for mill tailings and the decommissioning/closeout of uranium mines/mills; Annex II: Examples of national criteria for the exemption, release or cleanup of radioactive sites, buildings, equipment and materials from the decommissioning/closeout of uranium mines/mills; Annex III: Geotechnical, hydrological, environmental and economic rating matrix; Annex IV: Checklist for revegetation of decommissioned uranium tailings; Annex V: Longevity requirements; Annex VI: National experience in the decommissioning/closeout of facilities and residues from the mining and milling of radioactive ores.
Subject Classification: 0801 - Uranium ore processing; 0804 - Waste management
STI/DOC/010/364
ISBN: 92-0-101094-X
Publication Date: 24-6-1994
This handbook has been produced in collaboration with the International Union of Radioecologists. It should serve as a convenient and authoritative reference for radionuclide transfer parameter values used in biospheric assessment models. It supplements Safety Series No. 57 (1982), ''Generic Models and Parameters for Assessing the Environmental Transfer of Radio- nuclides from Routine Releases''. Contents: 1. Introduction; 2. Agricultural systems - vegetation; 3. Agricultural systems - milk, meat and eggs; 4. Freshwater ecosystems - fish; 5. Natural ecosystems; 6. Food processing transfer parameters.
Subject Classification: 0612 - Safety analysis; 1300 - Environment
STI/DOC/010/365
ISBN: 92-0-101394-9
Publication Date: 13-6-1994
This publication is the first comprehensive review of decontamination processes used throughout the world on water cooled reactors, i.e. PWRs, BWRs, HWRs and WWERs, operating under reduced dose while under maintenance and repair. It focuses on the following objectives: man-sievert reduction, plant life extension, fuel life extension, and general safety and materials reliability. In addition, special attention has been given to full system decontamination which is being developed in response to reactor ageing. Technical isssues such as materials compabitility, waste generation or recontamination after decontamination are also addressed. Contents: 1. Introduction; 2. Nature of oxides and contamination;3. Physical, mechanical and electrochemical decontamination processes; 4. Chemical decontamination processes; 5. Review of experience; 6. Technical issues.
Subject Classification: 0804 - Waste management
STI/DOC/010/366
ISBN: 92-0-101494-5
Publication Date: 5-12-1994
This report summarizes the results and conclusions of a survey, carried out by the IAEA, of existing waste management cost estimates for representative nuclear and fossil fuel cycles with the objective of providing a correct perspective of the economic and environmental aspects of the different means of electricity production. For the first time waste management cost estimates for all fuel cycle activities from mining to decommissioning of facilities have been compiled, and levelized unit costs for waste management have been compared to the total levelized costs for electricity production. Contents: 1. Introduction; 2. Description of fuel cycles; 3. Waste arisings; 4. Waste management; 5. Methodology for cost assessment; 6. Cost data; 7. Impact of waste management costs on electricity prices; 8. Comparison of impact of fossil and nuclear waste management costs on electricity prices; 9. Conclusions; Appendix I: Review of available references on fossil waste management cost estimates; Appendix II: Source data for nuclear waste management costs; Appendix III: Spreadsheet for reference data.
Subject Classification: 0804 - Waste management
STI/DOC/010/367
ISBN: 92-0-101594-1
Publication Date: 5-7-1994
This report provides guidance on current practices, documenting their strengths and weaknesses in dealing with the important issues of software engineering that nuclear power plant system designers, software producers and regulators are facing. It focuses on safety critical applications of general purpose processors controlled by custom developed software; however, it should also have application in safety related applications and in other types of computers. Contents: 1. Introduction; 2. Applicability of existing safety principles to software important to safety in nuclear power plants; 3. The engineering context; 4. Management; 5. Modelling for requirement analysis and design; 6. Documentation; 7. Pro- gramming; 8. Verification and validation; 9. Testing; 10. Figures of merit; 11. Maintenance; 12. Tool support; 13. Use of existing software; 14. Personnel qualification and training; 15. Balance in software based systems; Annex I: Existing standards and standardization work relating to software important to safety in nuclear power plants; Annex II: Application of software based systems important to safety in nuclear power plants: Experience of Member States.
Subject Classification: 0603 - Nuclear power plants
STI/DOC/010/368
ISBN: 92-0-101694-8
Publication Date: 13-7-1994
This guidebook provides a systematic, structured approach to the development and implementation of plant specific accident management programmes. It describes the major elements of accident management and their relationships, presents possible methods and techniques to solve specific problems and gives practical examples. Its main emphasis is on generic accident management guidelines, including evaluation of vulnerabilities, accident management strategies, symptom oriented emergency operating procedures, system utilization, training and organization. Contents: 1. Introduction; 2. Basic principles of accident management; 3. Framework for the development and implementation of an accident management programme; 4. Summary and conclusions; References; Annex I: Accident management directing principles; Annex II: Example of a guideline for the development of an accident management programme; Annex III: Example of application of the development of an accident management programme to a severe accident; Annex IV: Assessment of vulnerabilities; Annex V: Accident management procedures and guidance.
Subject Classification: 0610 - Accident response
STI/DOC/010/369
ISBN: 92-0-103194-7
Publication Date: 17-10-1994
The objective of this report is to facilitate a recognition of priority management issues which, when not adequately recognized and addressed, can result in problems in operational performance at nuclear power plants. It provides a number of effective practices, reflecting the positive experience of nuclear power companies, that have prevented or corrected problems related to selected management issues. Contents: Executive summary; 1. Introduction; 2. Generic issues related to effective management; 3. Effective practices; Annex 1:Designation of responsibility; Annex 2: Teamwork and effective communication; Annex 3: Effectiveness of engineering activities;Annex 4: Surveillance of items important to safety and reliability; Annex 5. Peer evaluation; Annex 6. Working level self-assessment; Annex 7: Corrective action programme; Annex 8: Monitoring of corrective actions; Annex 9: Performance oriented quality department; Annex 10: Assessment overview group; Annex 11: Integrated performance indicator system; Annex 12: Operating experience feedback; Annex 13: Self-assessment by the quality department; Annex 14: Focus on performance assessment; Annex 15: Quality maintenance teams; Annex 16: Performance enhancement standards; Annex 17: Performance based quality training; Annex 18: Prioritization of work; Annex 19: Profit centre concept; Annex 20: Departmental meeting policy; Annex 21: Plant modification information system; Annex 22: Negotiated business plan; Annex 23: Improvement of personnel qualification; Annex 24: Computerized maintenance management system; Annex 25: Information management; Annex 26: Feedback to design; Annex 27: Definition of interfaces; Annex 28: Teamwork and communication; Annex 29: Understanding of management goals; Annex 30: Relationship with the regulator; Annex 31: Interface with the regulator; Annex 32: Personal performance appraisal; Annex 33: Business plan of the nuclear organization; Annex 34: Management development training; Annex 35: Supervisory development programme; Annex 36: Monitoring of equipment condition; Annex 37: Career path programme.
Subject Classification: 0704 - Quality assurance
STI/DOC/010/370
ISBN: 92-0-104194-2
Publication Date: 19-12-1994
This report describes a wide spectrum of treatment processes of both aqueous and organic radioactive wastes. It briefly covers upgraded traditional and well proven processes such as chemical precipitation, ion exchange and evaporation, and focuses on rather new membrane and electrochemical processes and combinations of these processes. Methods based on the use of biological processes for the treatment of liquid radioactive wastes are described in this report for the first time. It also describes both advantages and disadvantages of the technologies mentioned. Contents: 1. Introduction; 2. Large scale applications of liquid waste treatment technologies; 3. Advances in technologies for the treatment of aqueous wastes; 4. Advances in technologies for the treatment of organic wastes; 5. Future trends in process development; Conclusions.
Subject Classification: 0804 - Waste management
STI/DOC/010/372
ISBN: 92-0-103394-X
Publication Date: 19-10-1994
This report addresses the development and implementation of computerized operator support systems (COSS) in nuclear installations. It discusses the requirements of operators in information management and job performance in control room environments. The design methodology described presents good practice approaches derived from the experience gained and the lessons learned during actual development of the COSS. Contents: 1. Introduction; 2. Computerized operator support systems; 3. Operational requirements; 4. Design methodology; 5. Verification and validation; 6. Implementation; 7. Licensing considerations; Appendix I: Classification scheme for man-machine activities; Appendix II: Techniques.
Subject Classification: 0702 - Nuclear power operations; 0703 - Reactor technology
STI/DOC/010/373
ISBN: 92-0-104094-6
Publication Date: 19-12-1994
This is the first report published by the IAEA which provides guidance on the preparation and implementation of the decommissioning of different types of research reactor. Different construction and operational features of research reactors have a major impact on the decommissioning techniques required. This report offers information on the conclusions drawn from a number of completed projects and identifies their similarities and differences. It is complemented by a computerized research reactor databank. Staff requirements, decommissioning costs waste activity are presented graphically according to reactor thermal power and integrated energy. Contents: 1. Introduction; 2. Classification of research reactors; 3. Responsibilities and stages of decommissioning; 4. Planning and management of decommissioning; 5. Regulatory aspects; 6. Technical aspects applicable to all types of research reactor; 7. Considerations specific to different types of research reactor; 8. Safety aspects; 9. Waste management; 10. Quality assurance; 11. Summary and conclusions; Appendix I: Reported research reactor decommissioning projects; Appendix II: Detailed data from research reactor decommissioning projects; Appendix III: Examples of the lessons learned from research reactor decommissioning projects.
Subject Classification: 0804 - Waste management
STI/DOC/010/375
ISBN: 92-0-100495-8
Publication Date: 26-5-1995
This publication gives a concise description of factors (safety-related, technical and economical) that are relevant to the selection of a decommissioning strategy, with particular reference to the safe enclosure option as a precursor to the dismantling of a nuclear installation. It is complemented by data on selected shut down installations. Aspects such as radioactive inventory, reasons for the chosen decommissioning strategy and systems kept operational or on stand-by are highlighted. Contents: 1. Introduction; 2. Objective; 3. Scope; 4. Structure; 5. Considerations influencing the choice of decommissioning strategy; 6. General overview of strategies and regulatory considerations; 7. Radiological considerations in safe enclosure; 8. Preparation for safe enclosure; 9. Management of safe enclosure; 10. Public safety and environmental aspects; 11. Summary and conclusions; Appendix: Problems of the application of safe enclosure in relation to various plant conditions; Annex A. Description of selected cases of safe enclosure.
Subject Classification: 0603 - Nuclear power plants; 0804 - Waste management
STI/DOC/010/376
ISBN: 92-0-100695-0
Publication Date: 20-6-1995
This publication describes requirements for and provides guidance (mostly gained by waste management agencies in the European Union and the USA) on quality assurance in the field of radioactive waste conditioning, from both the technological and regulatory points of view. It provides a logical basis for the application of quality assurance to the waste conditioning process, including container manufacture, waste immobilization and packaging, and to interrelated interim storage, transportation and disposal processes, with the purpose of ensuring the level of confidence required by the organizations concerned. Contents: 1. Introduction; 2. General principles of quality assurance in radioactive waste management; 3. Quality assurance programme considerations; 4. Management; 5. Performance; 6. Assessment; 7. Conclusions; Appendix I: Selective application and the graded approach; Appendix II: Important parameters of waste packages; Appendix III: Process control quality plan.
Subject Classification: 0804 - Waste management
STI/DOC/010/377
ISBN: 92-0-101195-4
Publication Date: 1-9-1995
Waste management at the back end of the nuclear fuel cycle comprises the various activities involved in the handling of the spent fuel once it has left the reactor. The purpose of the minimization of radioactive waste is threefold: (a) to reduce the risks of radiation exposure of technical personnel as well as of the public; (b) to reduce contamination of the environment; and (c) to reduce overall costs by reducing the repository space required for final waste disposal. Waste minimization has become a major part of waste management policies. Contents: 1. Introduction; 2. Waste minimization strategy; 3. Types and quantities of waste generated; 4. Practical waste minimization achievements; 5. Future trends; 6. Conclusions; References; Appendix A: Liquid and wet solid waste minimization techniques in LWRs; Appendix B: Dry solid waste minimization techniques in LWRs; Appendix C: General/administrative waste minimization techniques in LWRs.
Subject Classification: 0804 - Waste management
STI/DOC/010/378
ISBN: 92-0-101095-8
Publication Date: 24-7-1995
Spent fuel management encompasses all the activities associated with the handling, transport, storage, processing and eventual disposal of spent nuclear fuel following its discharge from the reactor. The time-scale for commitment to the safe management of spent fuel is expected to be several decades, until such time as the eventual disposal arrangements have been engineered. The purpose of this document is to assist Member States to establish policies and national arrangements for spent fuel management in a structured and timely manner. Contents: 1. Introduction; 2. Policy considerations and spent fuel management; 3. Regulatory framework for spent nuclear fuel management systems; 4. Making a choice between options; 5. Reprocessing technology; 6. Disposal technology; 7. Storage technology; 8. Conclusions.
Subject Classification: 0803 - Spent fuel management
STI/DOC/010/379
ISBN: 92-0-104096-2
Publication Date: 11-11-1996
be met and provides recommendations for the procedure of process selection and equipment design. Contents: 1. Introduction; 2. Design and operational objectives; 3. Basic safety aspects; 4. System requirements; 5. Conceptual design; 6. Subsystem requirements; 7. Component requirements; 8. Controls and instrumentation; 9. Building and physical arrangement; 10. System testing and commissioning; 11. System operation; 12. Documentation; Annex I: Waste source and characteristics; Annex II: Basic incineration concepts; Annex III: Basic off-gas treatment concepts.
Subject Classification: 0802 - Fuel fabrication and performance
STI/DOC/010/380
ISBN: 92-0-101496-1
Publication Date: 14-6-1996
This guidebook is a revision and update of the IAEA Guidebook on Training to Establish and Maintain the Qualification and Competence of Nuclear Power Plant Operations Personnel, IAEA-TECDOC-525, published in 1989. It incorporates the experience gained since the introduction of the Systematic Approach to Training (SAT) for nuclear power plant personnel and emphasizes a broader concept of competence which includes not only technical knowledge and skills but also knowledge, skills and attitudes related to human factors. In addition to the training of operating personnel, the Guidebook deals with the role and responsibilities of management; the training of management and maintenance personnel; organizations involved in training; and more effective and efficient methods of SAT analysis. Contents: 1. Introduction; 2. The role of management; 3. The role of training organizations and the organization of training; 4. SAT methodology overview; 5. Analysis; 6. Design; 7. Development; activities and technical co-operation in NPP personnel training and qualification.
Subject Classification: 0705 - Qualification and training of personnel
STI/PUB/023/31/01
Publication Date: 9-1-1991
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/31/02
Publication Date: 30-1-1991
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/31/03
Publication Date: 6-3-1991
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/01
Publication Date: 27-1-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/02
Publication Date: 26-2-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/03
Publication Date: 29-3-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/04
Publication Date: 18-5-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/05
Publication Date: 2-7-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/06
Publication Date: 12-8-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/07
Publication Date: 9-9-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/08
Publication Date: 13-10-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/09
Publication Date: 29-11-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/10
Publication Date: 22-12-1993
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/11
Publication Date: 21-1-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/33/12
Publication Date: 25-2-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/01
Publication Date: 8-4-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/02
Publication Date: 20-4-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/03
Publication Date: 19-5-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/04
Publication Date: 22-6-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/05
Publication Date: 5-7-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/06
Publication Date: 29-7-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/07
Publication Date: 29-8-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/08
Publication Date: 29-9-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/09
Publication Date: 17-10-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/10
Publication Date: 7-11-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/11
Publication Date: 25-11-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/34/12
Publication Date: 22-12-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/01
Publication Date: 30-1-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/02
Publication Date: 3-3-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/03
Publication Date: 23-3-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/04
Publication Date: 25-4-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/05
Publication Date: 24-5-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/06
Publication Date: 10-7-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/07
Publication Date: 24-7-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/08
Publication Date: 28-8-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/09
Publication Date: 21-9-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/10
Publication Date: 19-10-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/35/11
Publication Date: 13-11-1995
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/CUMI/1992
ISBN: 92-0-100692-6
Publication Date: 2-3-1992
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/SPS/1991
ISBN: 92-0-139091-2
Publication Date: 5-6-1991
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/023/SPS/1994
ISBN: 92-0-103594-2
Publication Date: 16-12-1994
Subject Classification: 0900 - Plasma physics and nuclear fusion
STI/PUB/1000
ISBN: 92-0-105295-2
Publication Date: 23-2-1996
This Safety Fundamentals publication provides a coherent set of objectives and principles for protection against ionizing radiation and for ensuring safety in the use of radiation sources. The protection objective and the safety objective, together with the eleven principles that have to be applied to achieve them, represent an international consensus. They provide the basis for the requirements in IAEA Safety Standards for the control of occupational, public and medical exposures and for the safety of sources. The Safety Fundamentals also provide an insight into the general system of protection and safety for those at senior levels in government and regulatory bodies and those responsible for making decisions relating to the uses of radiation in medicine, industry, agriculture, research and other areas. Contents: 1. Introduction; 2. Biological effects of irradiation; 3. Objectives of protection and safety; 4. Principles for practices; 5. Principles for intervention; 6. Implementation principles; 7. Infrastructure for protection and safety; Definitions. Chinese, French, Russian and Spanish editions in preparation.
Subject Classification: 0605 - Radiation sources and accelerators; 0609 - Radiation protection
STI/PUB/1016
ISBN: 92-0-103696-5
Publication Date: 11-10-1996
The revised Safety Code and its corresponding Safety Guides replace Safety Series No. 50-C-QA (Rev. 1), Code on the Safety of Nuclear Power Plants: Quality Assurance, and Safety Series Nos 50-SG-QA1 to 50-SG-QA11, and present new simplified basic requirements and implementation methods for quality assurance in a nuclear context. They provide recommendations to regulatory bodies in establishing regulatory requirements and in verifying their implementation, clearly formulate the responsibilities of the licensee in achieving improved quality and safety performance and give guidance on methods for fulfilling the basic requirements in a manner consistent with worldwide industry standards. Contents: Glossary; Code; Safety Guides.
Subject Classification: 0603 - Nuclear power plants; 0613 - Quality management; 0704 - Quality assurance
STI/PUB/1022
ISBN: 92-0-104396-1
Publication Date: 18-11-1996
Subject Classification: 0702 - Nuclear power operations
STI/PUB/245/22/01-24/1
Publication Date: 20-2-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/22/01-24/2
Publication Date: 13-3-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/22/01-24/3
Publication Date: 30-3-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/22/01-24/4
Publication Date: 31-3-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/22/01-24/5
Publication Date: 7-5-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/22/01-24/6
Publication Date: 28-5-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/22/01-24/7
Publication Date: 23-6-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/22/01-24/8
Publication Date: 26-6-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/22/01-24/9
Publication Date: 15-7-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/1
Publication Date: 25-2-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/2
Publication Date: 19-2-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/3
Publication Date: 15-3-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/4
Publication Date: 27-4-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/5
Publication Date: 14-5-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/6
Publication Date: 17-5-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/7
Publication Date: 18-5-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/8
Publication Date: 2-6-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/01-24/9
Publication Date: 10-6-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/12
Publication Date: 19-6-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/13
Publication Date: 1-7-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/14
Publication Date: 23-7-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/15
Publication Date: 6-8-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/16
Publication Date: 20-8-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/17
Publication Date: 9-9-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/18
Publication Date: 22-9-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/19
Publication Date: 5-10-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/20
Publication Date: 20-10-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/21
Publication Date: 11-11-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/22
Publication Date: 19-11-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/23
Publication Date: 27-11-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/23/24
Publication Date: 4-12-1992
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01
Publication Date: 13-1-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/1
Publication Date: 17-2-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/2
Publication Date: 28-2-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/3
Publication Date: 8-3-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/4
Publication Date: 8-3-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/5
Publication Date: 9-5-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/6
Publication Date: 21-3-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/7
Publication Date: 29-4-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/8
Publication Date: 31-5-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/01-24/9
Publication Date: 7-6-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/02
Publication Date: 27-1-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/03
Publication Date: 8-2-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/04
Publication Date: 24-2-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/05
Publication Date: 18-3-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/06
Publication Date: 19-3-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/07
Publication Date: 8-4-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/08
Publication Date: 19-4-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/09
Publication Date: 10-5-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/10
Publication Date: 13-5-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/11
Publication Date: 26-5-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/12
Publication Date: 14-6-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/13
Publication Date: 24-6-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/14
Publication Date: 8-7-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/15
Publication Date: 9-8-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/16
Publication Date: 16-8-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/17
Publication Date: 1-9-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/18
Publication Date: 15-9-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/19
Publication Date: 29-9-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/20
Publication Date: 22-10-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/21
Publication Date: 9-11-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/22
Publication Date: 23-11-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/23
Publication Date: 3-12-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/24/24
Publication Date: 7-12-1993
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01
Publication Date: 24-1-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 1
Publication Date: 31-1-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 2
Publication Date: 1-2-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 3
Publication Date: 1-2-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 4
Publication Date: 17-2-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 5
Publication Date: 27-2-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 6
Publication Date: 27-2-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 7
Publication Date: 7-3-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 8
Publication Date: 21-4-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/01-24 Part 9
Publication Date: 19-4-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/02
Publication Date: 24-1-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/03
Publication Date: 7-2-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/04
Publication Date: 21-2-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/05
Publication Date: 28-2-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/06
Publication Date: 23-3-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/07
Publication Date: 14-4-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/08
Publication Date: 29-4-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/09
Publication Date: 12-5-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/10
Publication Date: 18-5-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/11
Publication Date: 31-5-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/12
Publication Date: 8-6-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/13
Publication Date: 30-6-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/14
Publication Date: 12-7-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/15
Publication Date: 15-8-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/17
Publication Date: 5-9-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/18
Publication Date: 26-9-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/19
Publication Date: 6-10-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/20
Publication Date: 19-10-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/21
Publication Date: 16-11-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/22
Publication Date: 16-11-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/23
Publication Date: 1-12-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/25/24
Publication Date: 20-12-1994
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/01
Publication Date: 9-1-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/01-24 Part 5
Publication Date: 11-3-1996
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/02
Publication Date: 16-1-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/03
Publication Date: 31-1-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/04
Publication Date: 16-2-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/05
Publication Date: 7-3-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/06
Publication Date: 20-3-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/07
Publication Date: 18-4-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/08
Publication Date: 24-4-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/09
Publication Date: 10-5-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/10
Publication Date: 17-5-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/11
Publication Date: 26-5-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/12
Publication Date: 6-6-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/13
Publication Date: 27-6-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/15
Publication Date: 24-7-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/16
Publication Date: 18-8-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/17
Publication Date: 24-8-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/18
Publication Date: 18-9-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/19
Publication Date: 26-9-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/20
Publication Date: 4-10-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/21
Publication Date: 19-10-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/22
Publication Date: 8-11-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/26/23
Publication Date: 4-12-1995
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/27/02
Publication Date: 19-1-1996
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/27/03
Publication Date: 22-1-1996
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/27/05
Publication Date: 5-3-1996
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/27/06
Publication Date: 6-3-1996
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/27/16
Publication Date: 7-8-1996
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/27/17
Publication Date: 6-9-1996
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/245/27/18
Publication Date: 12-9-1996
Subject Classification: 1200 - International Nuclear Information System
STI/PUB/607
ISBN: 92-0-523091-X
Publication Date: 3-4-1991
Subject Classification: 0609 - Radiation protection
STI/PUB/618
ISBN: 92-0-523691-8
Publication Date: 14-1-1992
This guide outlines, for accidents at nuclear power plants, the principal elements in devising and implementing emergency plans so that actions in conjunction with national, regional and local government and other organizations ensure an orderly and timely decision making process and availability of essential personnel, equipment, supplies and services to limit the consequences of the emergency on the public. Contents: Introduction; Basis and content of the operating organization emergency plan; Emergency conditions; Organization for emergencies; Emergency facilities; Emergency measures; Aid to affected personnel; Termination of emergency; Maintaining emergency preparedness; Records; Annex I: Emergency plan implementing procedures; Annex II: Example of functional emergency organization on site; Annex III: Example of types of emergency equipment in the control room; Annex IV: Example of Emergency Control Centre equipment; Annex V: Example of types of emergency equipment stored on site; Annex VI: Example of logic diagram of site emergency arrangements; Annex VII: Use of stable iodine tablets for thyroid protection; Annex VIII: Example of types of emergency medical supplies available at the plant; Annex IX: Emergency kit and ambulance supplies; Annex X: Contamination control in transportation of casualties.
Subject Classification: 0603 - Nuclear power plants; 0610 - Accident response
STI/PUB/660
ISBN: 92-0-523791-4
Publication Date: 27-1-1992
This guide identifies the main objectives and responsibilities of management with respect to the safe operation of nuclear power plants. It discusses the factors to be considered in structuring the operating organization to meet these objectives, in assigning the responsibilities to units and individuals within the organization in an unambiguous manner, in establishing the management program-mes for ensuring that all safety requirements are met and in providing the services and facilities needed for the accomplishment of these tasks. Contents: Introduction; Management objectives and respon-sibilities; Structuring the operating organization; Management programmes; Information and liaison; Supporting functions; Appendix A: Development of instructions and procedures; Appendix B: Development of operating and maintenance procedures.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/687
ISBN: 92-0-523291-2
Publication Date: 13-1-1992
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/708
ISBN: 92-0-523891-0
Publication Date: 27-1-1992
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/709
ISBN: 92-0-523991-7
Publication Date: 3-2-1992
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/730
ISBN: 92-0-500192-9
Publication Date: 24-3-1992
Subject Classification: 0603 - Nuclear power plants
STI/PUB/734
ISBN: 92-0-523391-9
Publication Date: 27-1-1992
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; 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/802
ISBN: 92-0-523191-6
Publication Date: 17-4-1991
Subject Classification: 0603 - Nuclear power plants
STI/PUB/843
ISBN: 92-0-020091-5
Publication Date: 26-4-1991
Subject Classification: 0603 - Nuclear power plants; 0703 - Reactor technology
STI/PUB/847
ISBN: 92-0-400292-1
Publication Date: 26-5-1992
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/847
ISBN: 92-0-329091-5
Publication Date: 8-3-1991
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/847
ISBN: 92-0-229090-3
Publication Date: 25-2-1991
Subject Classification: 0609 - Radiation protection; 0610 - Accident response
STI/PUB/848
ISBN: 92-0-523491-5
Publication Date: 27-1-1992
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/848
ISBN: 92-0-400392-8
Publication Date: 17-6-1992
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/848
ISBN: 92-0-200192-8
Publication Date: 14-4-1992
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/848
ISBN: 92-0-323591-4
Publication Date: 23-10-1991
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: 92-0-200595-8
Publication Date: 6-10-1995
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/849
ISBN: 92-0-500292-5
Publication Date: 14-4-1992
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/849
ISBN: 92-0-400492-4
Publication Date: 17-6-1992
Subject Classification: 0603 - Nuclear power plants
STI/PUB/849
ISBN: 92-0-323691-0
Publication Date: 1-11-1991
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/856
ISBN: 92-0-123491-0
Publication Date: 4-2-1992
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/866
ISBN: 92-0-500193-7
Publication Date: 2-7-1993
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
Reglamento para el transporte seguro de materiales radioactivos. Edición de 1985 (enmendada en 1999)
STI/PUB/866
ISBN: 92-0-323091-2
Publication Date: 10-6-1991
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/866
ISBN: 92-0-423391-5
Publication Date: 1-11-1991
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/866
ISBN: 92-0-223091-9
Publication Date: 10-10-1991
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/867
ISBN: 92-0-500393-X
Publication Date: 16-7-1993
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/867
ISBN: 92-0-423491-1
Publication Date: 26-2-1992
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/867
ISBN: 92-0-200392-0
Publication Date: 12-10-1992
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/867
ISBN: 92-0-323191-9
Publication Date: 17-4-1991
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/868
ISBN: 92-0-500493-6
Publication Date: 16-7-1993
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/868
ISBN: 92-0-200492-7
Publication Date: 2-10-1992
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/868
ISBN: 92-0-323291-5
Publication Date: 31-5-1991
This publication is an updated version of the Third Edition of the Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (1985 Edition) and replaces all previous publications of Safety Series No. 37. It includes the changes to Safety Series No. 37 contained in Supplement 1988 to the Regulations for the Safe Transport of Radioactive Material as well as some modifications adopted by a Review Panel convened in Vienna in July 1989. 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: List of regulatory documents of international and regional international organizations; Appendix II: Contamination control; Appendix III: Half-life and specific activity of radionuclides, and specific activity of uranium and thorium; Appendix IV: Quality assurance in the safe transport of radioactive material; Appendix V: Guide for quality assurance programme; Appendix VI: Example calculations for establishing minimum segregation distance requirements; Appendix VII: Acceleration values and calculation methods for package tie-down forces; Appendix VIII: Example of a radiation protection programme for exclusive use vessels; Appendix IX: Influence of brittle fracture on material integrity; Appendix X: Criticality safety assessments.
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/868
ISBN: 92-0-423191-2
Publication Date: 23-9-1991
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/868
ISBN: 92-0-124090-2
Publication Date: 21-1-1991
This publication is an updated version of the Third Edition of the Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (1985 Edition) and replaces all previous publications of Safety Series No. 37. It includes the changes to Safety Series No. 37 contained in Supplement 1988 to the Regulations for the Safe Transport of Radioactive Material as well as some modifications adopted by a Review Panel convened in Vienna in July 1989. 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: List of regulatory documents of international and regional international organizations; Appendix II: Contamination control; Appendix III: Half-life and specific activity of radionuclides, and specific activity of uranium and thorium; Appendix IV: Quality assurance in the safe transport of radioactive material; Appendix V: Guide for quality assurance programme; Appendix VI: Example calculations for establishing minimum segregation distance requirements; Appendix VII: Acceleration values and calculation methods for package tie-down forces; Appendix VIII: Example of a radiation protection programme for exclusive use vessels; Appendix IX: Influence of brittle fracture on material integrity; Appendix X: Criticality safety assessments.
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/869
ISBN: 92-0-500293-3
Publication Date: 2-7-1993
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/869
ISBN: 92-0-200292-4
Publication Date: 3-7-1992
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/869
ISBN: 92-0-323391-1
Publication Date: 21-2-1991
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 1-13; 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/869
ISBN: 92-0-423091-6
Publication Date: 10-6-1991
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/870
ISBN: 92-0-300193-X
Publication Date: 26-4-1993
The safety objective, and basic and detailed requirements for the fulfillment of its safety function, are presented for the various types of emergency power systems. AC, DC, non-interruptible AC, standby diesel generators and non-electric systems such as steam turbines for individual pumps and instrument air, and the necessary distribution systems are dealt with. Some guidance is also given for the main and auxiliary outside grid connections. Contents: Definitions; 1. Introduction; 2. Power supplies; 3. General design principles; 4. General design requirements; 5. Detailed design requirements; 6. Design for surveillance, testing and maintenance; 7. Design confirmation; Annex I: Examples of tests, test intervals and monitoring displays; Annex II: Examples of electrical power supplies for a nuclear power plant with a single reactor.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/870
ISBN: 92-0-400193-3
Publication Date: 26-4-1993
The safety objective, and basic and detailed requirements for the fulfillment of its safety function, are presented for the various types of emergency power systems. AC, DC, non-interruptible AC, standby diesel generators and non-electric systems such as steam turbines for individual pumps and instrument air, and the necessary distribution systems are dealt with. Some guidance is also given for the main and auxiliary outside grid connections. Contents: Definitions; 1. Introduction; 2. Power supplies; 3. General design principles; 4. General design requirements; 5. Detailed design requirements; 6. Design for surveillance, testing and maintenance; 7. Design confirmation; Annex I: Examples of tests, test intervals and monitoring displays; Annex II: Examples ofelectrical power supplies for a nuclear power plant with a single reactor.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/870
ISBN: 92-0-200493-5
Publication Date: 15-7-1993
The safety objective, and basic and detailed requirements for the fulfillment of its safety function, are presented for the various types of emergency power systems. AC, DC, non-interruptible AC, standby diesel generators and non-electric systems such as steam turbines for individual pumps and instrument air, and the necessary distribution systems are dealt with. Some guidance is also given for the main and auxiliary outside grid connections. Contents: Definitions; 1. Introduction; 2. Power supplies; 3. General design principles; 4. General design requirements; 5. Detailed design requirements; 6. Design for surveillance, testing and maintenance; 7. Design confirmation; Annex I: Examples of tests, test intervals and monitoring displays; Annex II: Examples of electrical power supplies for a nuclear power plant with a single reactor.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/870
ISBN: 92-0-123291-8
Publication Date: 25-7-1991
The safety objective, and basic and detailed requirements for the fulfillment of its safety function, are presented for the various types of emergency power systems. AC, DC, non-interruptible AC, standby diesel generators and non-electric systems such as steam turbines for individual pumps and instrument air, and the necessary distribution systems are dealt with. Some guidance is also given for the main and auxiliary outside grid connections. Contents: Definitions; 1. Introduction; 2. Power supplies; 3. General design principles; 4. General design requirements; 5. Detailed design requirements; 6. Design for surveillance, testing and maintenance; 7. Design confirmation; Annex I: Examples of tests, test intervals and monitoring displays; Annex II: Examples ofelectrical power supplies for a nuclear power plant with a single reactor.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/871
ISBN: 92-0-300294-4
Publication Date: 9-6-1994
This guide puts the main emphasis on determining ground motion as an input to the design of a nuclear power plant and on determining any potential for surface faulting at a selected site. The type of information required and the investigations to be performed are described in the context of their dependence on the geological, seismological and geotectonical aspects of the region. Contents: Definitions; Note on the interpretation of the text; 1. Introduction; 2. General requirements; 3. Required information and investigations (Database); 4. Construction of a regional seismotectonic model; 5. Evaluation of design basis ground motions; 6. Potential for surface faulting at the site; 7. Seismically generated water waves; 8. Potential for permanent ground displacements associated with earthquakes and geological phenomena; Appendix: Seismic intensity scales.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/871
ISBN: 92-0-400194-1
Publication Date: 21-3-1994
This guide puts the main emphasis on determining ground motion as an input to the design of a nuclear power plant and on determining any potential for surface faulting at a selected site. The type of information required and the investigations to be performed are described in the context of their dependence on the geological, seismological and geotectonical aspects of the region. Contents: Definitions; Note on the interpretation of the text; 1. Introduction; 2. General requirements; 3. Required information and investigations (Database); 4. Construction of a regional seismotectonic model; 5. Evaluation of design basis ground motions; 6. Potential for surface faulting at the site; 7. Seismically generated water waves; 8. Potential for permanent ground displacements associated with earthquakes and geological phenomena; Appendix: Seismic intensity scales.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/871
ISBN: 92-0-200194-4
Publication Date: 12-5-1994
This guide puts the main emphasis on determining ground motion as an input to the design of a nuclear power plant and on determining any potential for surface faulting at a selected site. The type of information required and the investigations to be performed are described in the context of their dependence on the geological, seismological and geotectonical aspects of the region. Contents: Definitions; Note on the interpretation of the text; 1. Introduction; 2. General requirements; 3. Required information and investigations (Database); 4. Construction of a regional seismotectonic model; 5. Evaluation of design basis ground motions; 6. Potential for surface faulting at the site; 7. Seismically generated water waves; 8. Potential for permanent ground displacements associated with earthquakes and geological phenomena; Appendix: Seismic intensity scales.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/871
ISBN: 92-0-123191-1
Publication Date: 31-5-1991
This guide puts the main emphasis on determining ground motion as an input to the design of a nuclear power plant and on determining any potential for surface faulting at a selected site. The type of information required and the investigations to be performed are described in the context of their dependence on the geological, seismological and geotectonical aspects of the region. Contents: Definitions; Note on the interpretation of the text; 1. Introduction; 2. General requirements; 3. Required information and investigations (Database); 4. Construction of a regional seismotectonic model; 5. Evaluation of design basis ground motions; 6. Potential for surface faulting at the site; 7. Seismically generated water waves; 8. Potential for permanent ground displacements associated with earthquakes and geological phenomena; Appendix: Seismic intensity scales.
Subject Classification: 0603 - Nuclear power plants
Personnel des centrales nucléaires: Recrutement, formation et habilitation des agents d'exploitation
STI/PUB/874
ISBN: 92-0-203195-9
Publication Date: 9-2-1996
This guide outlines the factors to be considered to ensure that the operating organization has a sufficient number of qualified site personnel who are aware of their duties and responsibilities. It covers the organization for the nuclear power plant, the educational qualifications and experience of the persons recruited, the recruitment and training schedule, the training of operating personnel, the authorization of persons whose duties have an immediate bearing on safety, and re-training of personnel. Contents: Definitions; 1. Introduction; 2. Organizational plan; 3. Recruitment; 4. Training and qualification; 5. Authorization; 6. Records; Annex: Nuclear power plant organizational charts.
Subject Classification: 0603 - Nuclear power plants; 0705 - Qualification and training of personnel
STI/PUB/874
ISBN: 92-0-405095-0
Publication Date: 18-1-1996
This guide outlines the factors to be considered to ensure that the operating organization has a sufficient number of qualified site personnel who are aware of their duties and responsibilities. It covers the organization for the nuclear power plant, the educational qualifications and experience of the persons recruited, the recruitment and training schedule, the training of operating personnel, the authorization of persons whose duties have an immediate bearing on safety, and re-training of personnel. Contents: Definitions; 1. Introduction; 2. Organizational plan; 3. Recruitment; 4. Training and qualification; 5. Authorization; 6. Records; Annex: Nuclear power plant organizational charts.
Subject Classification: 0603 - Nuclear power plants; 0705 - Qualification and training of personnel
STI/PUB/874
ISBN: 92-0-302095-0
Publication Date: 5-10-1995
This guide outlines the factors to be considered to ensure that the operating organization has a sufficient number of qualified site personnel who are aware of their duties and responsibilities. It covers the organization for the nuclear power plant, the educational qualifications and experience of the persons recruited, the recruitment and training schedule, the training of operating personnel, the authorization of persons whose duties have an immediate bearing on safety, and re-training of personnel. Contents: Definitions; 1. Introduction; 2. Organizational plan; 3. Recruitment; 4. Training and qualification; 5. Authorization; 6. Records; Annex: Nuclear power plant organizational charts.
Subject Classification: 0603 - Nuclear power plants; 0705 - Qualification and training of personnel
STI/PUB/874
ISBN: 92-0-123391-4
Publication Date: 30-7-1991
This guide outlines the factors to be considered to ensure that the operating organization has a sufficient number of qualified site personnel who are aware of their duties and responsibilities. It covers the organization for the nuclear power plant, the educational qualifications and experience of the persons recruited, the recruitment and training schedule, the training of operating personnel, the authorization of persons whose duties have an immediate bearing on safety, and re-training of personnel. Contents: Definitions; 1. Introduction; 2. Organizational plan; 3. Recruitment; 4. Training and qualification; 5. Authorization; 6. Records; Annex: Nuclear power plant organizational charts.
Subject Classification: 0603 - Nuclear power plants; 0705 - Qualification and training of personnel
STI/PUB/877
ISBN: 92-0-150091-2
Publication Date: 21-8-1991
Proceedings of a Senior Expert symposium jointly organized by CEC, CMEA, ECE, IAEA, IEA, IIASA, OECD/NEA, UNEP, IBRO, WHO, and WMO, in co-operation with the Government of Finland, Helsinki, 1317 May 1991. The objective of the symposium was to provide a comprehensive assessment of the environmental and health factors as well as the economic factors involved in supplying electricity services, and to suggest a framework within which these issues should be taken into account in making future plans and decisions on electricity production and use. The potential role of different ways of meeting electricity service requirements was also analysed, taking into consideration both demand side and supply options in the light of their comparative economic, environmental and health related impacts. Contents: Opening session; Energy and electricity supply and demand: Implications for the global environment; Energy sources and technologies for electricity generation; Comparative environmental and health effects of different energy systems for electricity generation; Incorporation of environmental and health impacts into policy, planning and decision making for the electricity sector; Luncheon sessions; Policy aspects of electricity and the environment; Key issues and findings and round table on challenges for international co-operation.
Subject Classification: 0612 - Safety analysis; 0700 - Nuclear power; 1300 - Environment
STI/PUB/878
ISBN: 92-0-000292-7
Publication Date: 23-3-1992
Proceedings of a symposium jointly organized with ANS, ENS and OECD/NEA, Vienna, 37 June 1991. During recent years the development of PSA has been directed towards its use as a practical tool for the enhancement of operational safety. Only plant specific analysis can provide a basis for meaningful risk management. The importance of human interventions in the recovery from degraded states of operation, the importance of inclusion of external events in PSA, the determination of potentials for common cause failures and the importance of treating and communicating the uncertainties have already been well established within the PSA community. Also, risks during low power level and shutdown states have become more recognized. Contents: Opening remarks and invited papers; Methodology; Regulatory applications; PSA use and applications Part I; Applications to process facilities and international activities; Operating experience and ageing; PSA use and applications Part II; PSA results and insights Part I; Common cause and external events; PSA results and insights Part II; Human factors; Living PSA; PSA level 2 and level 3; Poster presentations; Summary, conclusions and recommendations; Closing session.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/880
ISBN: 92-0-100292-0
Publication Date: 7-2-1992
Proceedings of a conference, Vienna, 26 September 1991. The conference was directed to decision makers on nuclear safety and energy policy at the technical policy level. Its objective was to review the nuclear power safety issues on which international consensus would be desirable, to address the concerns on nuclear safety expressed by the United Nations World Commission on Environment and Development, and to formulate recommendations for future actions by national and international authorities to advance nuclear safety to the highest level, including proposals for future IAEA activities. The major issues under discussion were: fundamental principles for the safe use of nuclear power; ensuring and enhancing safety of operating plants; approach to nuclear power plants built to earlier safety standards; the next generation of nuclear power plants; and final disposal of radioactive waste. Contents: Opening speeches; Issue overviews, summary discussions of substantive topics, conclusions and recommendations; Major findings of the conference and presidents closing statement; Background papers; Authorities of the conference and list of participants.
Subject Classification: 0603 - Nuclear power plants; 0611 - Radioactive waste management
STI/PUB/882
ISBN: 92-0-323491-8
Publication Date: 23-10-1991
This report by the IAEA's International Nuclear Safety Advisory Group INSAG describes the concept of 'Safety Culture' in connection with nuclear plant safety in relation to both organi- zations and individuals engaged in nuclear power activities. It provides a basis for judging the effectiveness of the safety culture in specific cases in order to identify potential improvements. Contents: Summary; 1. Introduction; 2. Definition and character of Safety Culture; 3.1. Requirements at policy level; 3.2. Requirements on managers; 3.3. Response of individuals; 4. Tangible evidence; 4.1. Government and its organizations; 4.2. Operating organization; 4.3. Supporting organizations; 5. Concluding comments; Appendix: Safety Culture indicators.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/882
ISBN: 92-0-423291-9
Publication Date: 5-9-1991
Subject Classification: 0603 - Nuclear power plants
STI/PUB/882
ISBN: 92-0-223191-5
Publication Date: 23-10-1991
This report by the IAEA's International Nuclear Safety Advisory Group INSAG describes the concept of 'Safety Culture' in connection with nuclear plant safety in relation to both organi- zations and individuals engaged in nuclear power activities. It provides a basis for judging the effectiveness of the safety culture in specific cases in order to identify potential improvements. Contents: Summary; 1. Introduction; 2. Definition and character of Safety Culture; 3.1. Requirements at policy level; 3.2. Requirements on managers; 3.3. Response of individuals; 4. Tangible evidence; 4.1. Government and its organizations; 4.2. Operating organization; 4.3. Supporting organizations; 5. Concluding comments; Appendix: Safety Culture indicators.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/882
ISBN: 92-0-123091-5
Publication Date: 15-2-1991
This report by the IAEAs International Nuclear Safety Advisory Group INSAG describes the concept of Safety Culture in connection with nuclear plant safety in relation to both organi- zations and individuals engaged in nuclear power activities. It provides a basis for judging the effectiveness of the safety culture in specific cases in order to identify potential improvements. Contents: Summary; 1. Introduction; 2. Definition and character of Safety Culture; 3.1. Requirements at policy level; 3.2. Requirements on managers; 3.3. Response of individuals; 4. Tangible evidence; 4.1. Government and its organizations; 4.2. Operating organization; 4.3. Supporting organizations; 5. Concluding comments; Appendix: Safety Culture indicators.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/884
ISBN: 92-0-129091-8
Publication Date: 17-5-1991
Subject Classification: 0609 - Radiation protection; 0610 - Accident response; 0612 - Safety analysis
STI/PUB/885
ISBN: 92-0-400192-5
Publication Date: 13-3-1992
Subject Classification: 0609 - Radiation protection; 0610 - Accident response; 0612 - Safety analysis
STI/PUB/885
ISBN: 92-0-129191-4
Publication Date: 14-9-1991
Subject Classification: 0609 - Radiation protection; 0610 - Accident response; 0612 - Safety analysis
STI/PUB/887
ISBN: 92-0-105092-5
Publication Date: 8-1-1993
This publication contains the questions which must be posed by the safety assessor when reviewing the safety of an emergency power system in the design of a nuclear power plant. lt relates directly to the safety requirements as laid down in Safety Series No. 50-SG-D7 so that it is possible to confirm the compliance of a design to the safety requirements. An extensive reference list of relevant international and national technical standards provides further guidance on acceptable design solutions. Contents: 1. Introduction; 2. Safety assessment and licensing; 3. Safety assessment and review guidance; 4. Reference list of recommended information for the safety assessment; 5. Bibliography.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/888
ISBN: 92-0-102392-8
Publication Date: 7-8-1992
This safety practice report provides guidance on conducting a Level 1 PSA for internal events in nuclear power plants. The main emphasis is on the procedural steps of the PSA rather than the details of the corresponding methods. The report is intended to assist technical persons managing or performing PSAs. A particular aim is to promote a standardized framework, terminology and form of documentation for PSAs so as to facilitate external review of the results. The report not only describes methods, but also considers advantages and limitations of various approaches and indicates those most widely used to date. Contents: 1. Introduction; 2. Management and organization; 3. Identification of sources of radioactive releases and accident initiators; 4. Accident sequence modelling; 5. Data assessment and parameter estimation; 6. Accident sequence quantification; 7. Documentation of the analysis: Display and interpretation of results; Appendix I: Example of a typical schedule for a Level 1 PSA; Appendix II: Contents of work specification.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/894
ISBN: 92-0-129391-7
Publication Date: 13-9-1991
Subject Classification: 0609 - Radiation protection; 0612 - Safety analysis
STI/PUB/896
ISBN: 92-0-101692-1
Publication Date: 17-6-1992
Since the 1950s, gamma and electron beam facilities have been used for medical, industrial and research purposes, and their safety record has been very good. With the publication of this book, international, harmonized safety guidance is available for all those involved in the design, control and safe use of this type of irradiation facility. Subject areas such as the classification of irradiators, regulatory control and special procedures are covered and the safety philosophy for all types of irradiators is explained. Contents: 1. Introduction; 2. Types of irradiators; 3. Radiation safety objectives; 4. Safety philosophy; 5. Design requirements; 6. Regulatory control; 7. Responsibilities of the operating organization; 8. Responsibilities of designers and manufacturers, importers and suppliers, and constructors and installers; 9. The transport, loading and unloading of sources; 10. Special safety requirements for electron accelerator facilities; 11. Emergency response planning; References; Glossary.
Subject Classification: 0605 - Radiation sources and accelerators
STI/PUB/897
ISBN: 92-0-101892-4
Publication Date: 25-6-1992
This guide points out the necessity of measures for protecting plant items which are important to safety against fires of internal and external origin. Fire, being a real threat to nuclear safety, should receive adequate attention from the beginning of the design process throughout the life of a plant. The present guide was developed to enlarge on the general requirements given in the Code on the Safety of Nuclear Power Plants: Design, Safety Series No. 50-SG-D (Rev. 1), published in 1988. Contents: Definitions; 1. Introduction; 2. General fire protection requirements; 3. Fire protection design approach; 4. Fire prevention; 5. Fire detection and extinguishing; 6. Mitigation of secondary fire effects; 7. Quality assurance; 8. Operational aspects of manual fire fighting; Appendix I: Halon fire extinguishing systems; Appendix II: Escape routes; Annex I: Additional guidance on the preparation of fire hazards analyses; Annex II: Fire barriers; Annex III: List of controls; Annex IV: Fire detection systems; Annex V: Automatic sprinkler and water spray systems; Annex VI: Example of possible layout of fire water supply system; Annex VII: Schematic examples of compartment separation for ventilation; Annex VIII: Electrical cable insulation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/902
ISBN: 92-0-123591-7
Publication Date: 27-1-1992
This publication provides guidance on data requirements and an effective and practical system for data collection and record keeping in relation to the evaluation and management of ageing and service life of nuclear power plant components. The application of the guidance will contribute to the safe and reliable operation of nuclear power plants and will facilitate international information exchange on ageing related component failures, malfunctions and degradation, since data collected using the same ground rules are easier to exchange and compare. Contents: 1. Introduction; 2. General data needs for the evaluation and management of ageing; 3. Attributes of an effective data collection and record keeping system; 4. General recommendations for implementing the proposed data collection and record keeping system; Appendix I: Component specific data needs; Appendix II: Examples of effective data collection and record keeping systems; Appendix III: Guidance for implementation of an advanced data collection and record keeping system; References; Glossary.
Subject Classification: 0603 - Nuclear power plants; 0702 - Nuclear power operations
STI/PUB/903
ISBN: 92-0-159391-0
Publication Date: 13-9-1991
Subject Classification: 0702 - Nuclear power operations
STI/PUB/907
ISBN: 92-0-000193-9
Publication Date: 7-5-1993
Proceedings of a symposium organized jointly with CEC and OECD/NEA, Antwerp, Belgium, 1923 October 1992. The purpose of the symposium was to review the progress being made in national and international programmes towards the demonstration of safe disposal of radioactive wastes. The technical presentations addressed disposal in all the principal geological media currently under consideration: clay, crystalline rock, salt and volcanic tuff. The programmes described ranged from national screening surveys on a broad, regional scale to detailed site specific investigations in underground research laboratories. Contents: Keynote address; Programmes of international organizations; Site characterization programmes and methods; Repository design concepts, construction techniques and engineered barrier design; Characterization and acceptance of high level and alpha bearing wastes; Repository concepts for direct disposal of spent fuel; Developing, testing and validating repository performance assessment models; National and international programmes; Poster presentations.
Subject Classification: 0608 - Waste repositories; 0611 - Radioactive waste management; 0803 - Spent fuel management; 0804 - Waste management
STI/PUB/910
ISBN: 92-0-400294-8
Publication Date: 18-5-1994
This report gives an account of the history of nuclear power plant safety, covering the important elements from safety in the earliest days to lessons learned from accidents and current reactor safety principles. The report concentrates on light and heavy water moderated reactors, by far the most prevalent types. It concludes that for these types of reactors, levels of safety are in reasonable agreement with the present INSAG quantitative targets for probabilities of core melt and radioactive releases. The report is directed at an educated general public. Contents: Summary; Prologue; 1. Important elements of the history of nuclear plant safety; 2. Current reactor safety principles; 3. Safety of nuclear plants; 4. Nuclear fuel cycle; 5. Features desired in future plants; 6. Continued improvement of nuclear power plant safety; 7. Conclusions; Appendix I: IAEA safeguards against proliferation of nuclear weapons; Appendix II: Nuclear reactor radiation and its effects; Appendix III: Relative health risks in electricity generation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/910
ISBN: 92-0-300293-6
Publication Date: 13-12-1993
This report gives an account of the history of nuclear power plant safety, covering the important elements from safety in the earliest days to lessons learned from accidents and current reactor safety principles. The report concentrates on light and heavy water moderated reactors, by far the most prevalent types. It concludes that for these types of reactors, levels of safety are in reasonable agreement with the present INSAG quantitative targets for probabilities of core melt and radioactive releases. The report is directed at an educated general public. Contents: Summary; Prologue; 1. Important elements of the history of nuclear plant safety; 2. Current reactor safety principles; 3. Safety of nuclear plants; 4. Nuclear fuel cycle; 5. Features desired in future plants; 6. Continued improvement of nuclear power plant safety; 7. Conclusions; Appendix I: IAEA safeguards against proliferation of nuclear weapons; Appendix II: Nuclear reactor radiation and its effects; Appendix III: Relative health risks in electricity generation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/910
ISBN: 92-0-200393-9
Publication Date: 23-4-1993
This report gives an account of the history of nuclear power plant safety, covering the important elements from safety in the earliest days to lessons learned from accidents and current reactor safety principles. The report concentrates on light and heavy water moderated reactors, by far the most prevalent types. It concludes that for these types of reactors, levels of safety are in reasonable agreement with the present INSAG quantitative targets for probabilities of core melt and radioactive releases. The report is directed at an educated general public. Contents: Summary; Prologue; 1. Important elements of the history of nuclear plant safety; 2. Current reactor safety principles; 3. Safety of nuclear plants; 4. Nuclear fuel cycle; 5. Features desired in future plants; 6. Continued improvement of nuclear power plant safety; 7. Conclusions; Appendix I: IAEA safeguards against proliferation of nuclear weapons; Appendix II: Nuclear reactor radiation and its effects; Appendix III: Relative health risks in electricity generation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/910
ISBN: 92-0-100192-4
Publication Date: 27-2-1992
This report gives an account of the history of nuclear power plant safety, covering the important elements from safety in the earliest days to lessons learned from accidents and current reactor safety principles. The report concentrates on light and heavy water moderated reactors, by far the most prevalent types. It concludes that for these types of reactors, levels of safety are in reasonable agreement with the present INSAG quantitative targets for probabilities of core melt and radioactive releases. The report is directed at an educated general public. Contents: Summary; Prologue; 1. Important elements of the history of nuclear plant safety; 2. Current reactor safety principles; 3. Safety of nuclear plants; 4. Nuclear fuel cycle; 5. Features desired in future plants; 6. Continued improvement of nuclear power plant safety; 7. Conclusions; Appendix I: IAEA safeguards against proliferation of nuclear weapons; Appendix II: Nuclear reactor radiation and its effects; Appendix III: Relative health risks in electricity generation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/911
ISBN: 92-0-101492-9
Publication Date: 12-5-1992
This safety report establishes guidelines on the role that probabilistic safety assessment can play as part of an overall safety assurance programme in nuclear power plants. It also describes a framework for probabilistic safety criteria (PSC) and provides guidance for the establishment of PSC values. Contents: 1. Introduction; 2. The role of PSA; 3. PSA management, methodology and documentation; 4. Development of PSC; References; Glossary.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/913
ISBN: 92-0-201796-4
Publication Date: 19-12-1996
The purpose of this report is to update findings of the Inter- national Nuclear Safety Advisory Group's Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident (INSAG-1), published in September 1986, in the light of further information that has been revealed since that meeting. INSAG stands by the general conclusions of INSAG-1 about the accident's causes and their implications for the safety of the Chernobyl type light water cooled graphite moderated RBMK reactors. However, the new information, which derives from studies made in the then USSR on the physical origins of the accident, has led INSAG to shift the emphasis of its conclusions from the actions of the operating staff to faulty design of the reactor's control rods and safety systems. Deficiencies in the regulation and management of safety matters throughout the Soviet nuclear power industry have also been revealed and are discussed. Two detailed Soviet reports on the causes and circumstances of the Chernobyl accident, translated into English by the IAEA, and a statement of measures that have been taken to enhance the safety of RBMK reactors are included. Contents: 1. Introduction; 2. Features of the reactor; 3. The accident; 4. More recent analyses of the fault scenario; 5. Views of INSAG; 6. Conclusions on factors contributory to the accident; Appendix: Measures to improve the safety of RBMK plants; Annex I: Report by a commission to the USSR State Committee for the supervision of safety in industry and nuclear power; Annex II: Report by a working group of USSR experts.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/913
ISBN: 92-0-300194-8
Publication Date: 24-2-1994
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/913
ISBN: 92-0-400593-9
Publication Date: 13-12-1993
The purpose of this report is to update findings of the International Nuclear Safety Advisory Group's Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident (INSAG-1), published in September 1986, in the light of further information that has been revealed since that meeting. INSAG stands by the general conclusions of INSAG-1 about the accident's causes and their implications for the safety of the Chernobyl type light water cooled graphite moderated RBMK reactors. However, the new information, which derives from studies made in the then USSR on the physical origins of the accident, has led INSAG to shift the emphasis of its conclusions from the actions of the operating staff to faulty design of the reactor's control rods and safety systems. Deficiencies in the regulation and management of safety matters throughout the Soviet nuclear power industry have also been revealed and are discussed. Two detailed Soviet reports on the causes and circumstances of the Chernobyl accident, translated into English by the IAEA, and a statement of measures that have been taken to enhance the safety of RBMK reactors are included. Contents: 1. Introduction; 2. Features of the reactor; 3. The accident; 4. More recent analyses of the fault scenario; 5. Views of INSAG; 6. Conclusions on factors contributory to the accident; Appendix: Measures to improve the safety of RBMK plants; Annex I: Report by a commission to the USSR State Committee for the supervision of safety in industry and nuclear power; Annex II: Report by a working group of USSR experts.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/913
ISBN: 92-0-104692-8
Publication Date: 11-1-1993
The purpose of this report is to update findings of the International Nuclear Safety Advisory Groups Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident (INSAG-1), published in September 1986, in the light of further information that has been revealed since that meeting. INSAG stands by the general conclusions of INSAG-1 about the accidents causes and their implications for the safety of the Chernobyl type light water cooled graphite moderated RBMK reactors. However, the new information, which derives from studies made in the then USSR on the physical origins of the accident, has led INSAG to shift the emphasis of its conclusions from the actions of the operating staff to faulty design of the reactors control rods and safety systems. Deficiencies in the regulation and management of safety matters throughout the Soviet nuclear power industry have also been revealed and are discussed. Two detailed Soviet reports on the causes and circumstances of the Chernobyl accident, translated into English by the IAEA, and a statement of measures that have been taken to enhance the safety of RBMK reactors are included. Contents: 1. Introduction; 2. Features of the reactor; 3. The accident; 4. More recent analyses of the fault scenario; 5. Views of INSAG; 6. Conclusions on factors contributory to the accident; Appendix: Measures to improve the safety of RBMK plants; Annex I: Report by a commission to the USSR State Committee for the supervision of safety in industry and nuclear power; Annex II: Report by a working group of USSR experts.
Subject Classification: 0603 - Nuclear power plants; 0612 - Safety analysis
STI/PUB/916
ISBN: 92-0-300494-7
Publication Date: 16-11-1994
Probabilistic safety assessment (PSA) has contributed significantly to the understanding of how best to ensure the safety of nuclear power plants. By means of PSA a nuclear power plant, including its safety systems and installations, can be analysed in its entirety. The rapid development of the method has resulted in its extensive use. This report reviews the general bases of PSA, emphasizing its merits and limits as well as the general lines of the future development of that methodology and its applications. Contents: 1. Introduction; 2. Capabilities and limitations of the methodology of PSA; 3. Further development of methodology; 4. Guidelines for presentation and interpretation of PSA results; 5. How should PSA be used in the future?; 6. Conclusions.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/916
ISBN: 92-0-400394-4
Publication Date: 16-11-1994
Probabilistic safety assessment (PSA) has contributed significantly to the understanding of how best to ensure the safety of nuclear power plants. By means of PSA a nuclear power plant, including its safety systems and installations, can be analysed in its entirety. The rapid development of the method has resulted in its extensive use. This report reviews the general bases of PSA, emphasizing its merits and limits as well as the general lines of the future development of that methodology and its applications. Contents: 1. Introduction; 2. Capabilities and limitations of the methodology of PSA; 3. Further development of methodology; 4. Guidelines for presentation and interpretation of PSA results; 5. How should PSA be used in the future?; 6. Conclusions.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/916
ISBN: 92-0-200294-0
Publication Date: 1-7-1994
Probabilistic safety assessment (PSA) has contributed significantly to the understanding of how best to ensure the safety of nuclear power plants. By means of PSA a nuclear power plant, including its safety systems and installations, can be analysed in its entirety. The rapid development of the method has resulted in its extensive use. This report reviews the general bases of PSA, emphasizing its merits and limits as well as the general lines ofthe future development of that methodology and its applications. Contents: 1. Introduction; 2. Capabilities and limitations of the methodology of PSA; 3. Further development of methodology; 4. Guidelines for presentation and interpretation of PSA results; 5. How should PSA be used in the future?; 6. Conclusions.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/916
ISBN: 92-0-102492-4
Publication Date: 21-7-1992
Probabilistic safety assessment (PSA) has contributed significantly to the understanding of how best to ensure the safety of nuclear power plants. By means of PSA, a nuclear power plant, including its safety systems and installations, can be analysed in its entirety. The rapid development of the method has resulted in its extensive use. This report reviews the general bases of PSA, emphasizing its merits and limits as well as the general lines of the future development of that methodology and its applications. Contents: 1. Introduction; 2. Capabilities and limitations of the methodology of PSA; 3. Further development of methodology; 4. Guidelines for presentation and interpretation of PSA results; 5. How should PSA be used in the future?; 6. Conclusions.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/917
ISBN: 92-0-103592-6
Publication Date: 5-11-1992
This guide was originally issued as Safety Guide No. 50-SG-S2. It provides details on the design of a nuclear power plant such that earthquakes at the site determined according to Safety Guide No. 50-SG-S1 will not jeopardize its safety. It gives guidance on methods and procedures for analysing, testing and qualifying structures and equipment such that they fulfil the purpose foreseen in the design. Contents: Definitions; 1. Introduction; 2. General concept; 3. Seismic design; 4. Seismic qualification: Analysis, testing, earthquake experience and indirect methods; 5. Seismic instrumentation; Appendix I: Methods of seismic analysis; Appendix II: Modelling techniques; Annex I: Examples of lists of seismic category I and other category items; Annex II: Sloshing and impulse effects in liquid containers.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/921
ISBN: 92-0-103292-7
Publication Date: 12-10-1992
The purpose of this Safety Guide is to provide safety guidance for the design and operation of radioactive waste incineration facilities. The Safety Guide emphasizes the design objectives and system requirements to be met and provides recommendations for the procedure of process selection and equipment design. Contents: 1. Introduction; 2. Design and operational objectives; 3. Basic safety aspects; 4. System requirements; 5. Conceptual design; 6. Subsystem requirements; 7. Component requirements; 8. Controls and instrumentation; 9. Building and physical arrangement; 10. System testing and commissioning; 11. System operation; 12. Documentation; Annex I: Waste source and characteristics; Annex II: Basic incineration concepts; Annex III: Basic off-gas treatment concepts.
Subject Classification: 0611 - Radioactive waste management
STI/PUB/923
ISBN: 92-0-103492-X
Publication Date: 18-9-1992
Subject Classification: 0702 - Nuclear power operations
STI/PUB/924
ISBN: 92-0-104992-7
Publication Date: 8-1-1993
This Safety Practices publication, a part of the lAEAs Radioactive Waste Safety Standards (RADWASS) programme, provides guidance on those application of internationally agreed principles for determining those levels of radionuclides in materials below which they can be exempted from regulatory control and can be recycled or reused without any further restriction. lt illustrates a methodology by which practical exempt quantities for the recycle and reuse of these materials may be derived and gives typical exempt values based on a generic assessment. Contents: 1. Introduction; 2. Exemption from regulatory control applied to recycle and reuse; 3. Recycle and reuse as options; 4. Methods for dose assessment; 5. Recycle scenarios and related assumptions; 6. Derived exemption levels; 7. Additional considerations and discussion of the results; 8. Summary; References; Appendix I. Methods for estimating individual and collective doses from external exposures to radionuclides during recycle and reuse; Appendix II. Methods for estimating individual and collective doses from inhalation and ingestion of radioactive materials; Appendix III. Estimated individual and collective effective dose equivalents by scenario and pathway for concentrations of 1 Bq/g of each reference radionuclide for the recycle and reuse of contaminated materials.
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/925
ISBN: 92-0-101693-X
Publication Date: 19-7-1993
Subject Classification: 0605 - Radiation sources and accelerators; 0609 - Radiation protection; 0610 - Accident response
STI/PUB/927
ISBN: 92-0-300292-8
Publication Date: 14-1-1993
This publication presents international consensus principles useful in the design of a research reactor. lt is complemented by Safety Series No. 35-S2, Code on the Safety of Nuclear Research Reactors: Operation. Both publications provide an overview on basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies. Contents: Definitions; 1. Introduction; 2. Safety objectives; 3. Regulatory supervision; 4. Siting requirements; 5. General design requirements; 6. Specific design requirements; Appendix: Selected postulated initiating events; Annex: Selected safety functions.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/927
ISBN: 92-0-400592-0
Publication Date: 14-1-1993
This publication presents international consensus principles useful in the design of a research reactor. It is complemented by Safety Series No. 35-S2, Code on the Safety of Nuclear Research Reactors: Operation. Both publications provide basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies. Contents: Definitions; 1. Introduction; 2. Safety objectives; 3. Regulatory supervision; 4. Siting requirements; 5. General design requirements; 6. Specific design requirements; Appendix: Selected postulated initiating events; Annex: Selected safety functions.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/927
ISBN: 92-0-200193-6
Publication Date: 23-4-1993
This publication presents international consensus principles useful in the design of a research reactor. lt is complemented by Safety Series No. 35-S2, Code on the Safety of Nuclear Research Reactors: Operation. Both publications provide an overview on basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies. Contents: Definitions; 1. Introduction; 2. Safety objectives; 3. Regulatory supervision; 4. Siting requirements; 5. General design requirements; 6. Specific design requirements; Appendix: Selected postulated initiating events; Annex: Selected safety functions.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/927
ISBN: 92-0-104292-2
Publication Date: 14-1-1993
This publication presents international consensus principles useful in the design of a research reactor. It is complemented by Safety Series No. 35-S2, Code on the Safety of Nuclear Research Reactors: Operation. Both publications provide basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies. Contents: Definitions; 1. Introduction; 2. Safety objectives; 3. Regulatory supervision; 4. Siting requirements; 5. General design requirements; 6. Specific design requirements; Appendix: Selected postulated initiating events; Annex: Selected safety functions.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/928
ISBN: 92-0-300392-4
Publication Date: 14-1-1993
This publication presents international consensus principles useful in the operation of a research reactor. lt is complemented by Safety Series No. 35-S1, Code on the Safety of Nuclear Research Reactors: Design. Both publications provide an overview on basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies. Contents: Definitions; 1. Introduction; 2. Safety objectives; 3. Regulatory supervision; 4. Responsibilities for safe operation; 5. Safety analysis for operation; 6. Operational limits and conditions; 7. Operating procedures; 8. Commissioning; 9. Maintenance, period testing and inspection; 10. Core management and fuel handling; 11. Records and reports; 12. Reactor utilization; 13. Modifications; 14. Radioactive wastes; 15. Radiation protection; 16. Emergency planning; 17. Security; 18. Quality assurance; 19. Decommissioning; Annex: Examples of operational aspects of research reactors that require particular attention in a quality assurance programme.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/928
ISBN: 92-0-400692-7
Publication Date: 14-1-1993
This publication presents international consensus principles useful in the operation of a research reactor. It is complemented by Safety Series No. 35-S1, Code on the Safety of Nuclear Research Reactors: Design. Both publications provide basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies. Contents: Definitions; 1. Introduction; 2. Safety objectives; 3. Regulatory supervision; 4. Responsibilities for safe operation; 5. Safety analysis for operation; 6. Operational limits and conditions; 7. Operating procedures; 8. Commissioning; 9. Maintenance, period testing and inspection; 10. Core management and fuel handling; 11. Records and reports; 12. Reactor utilization; 13. Modifications; 14. Radioactive wastes; 15. Radiation protection; 16. Emergency planning; 17. Security; 18. Quality assurance; 19. Decommissioning; Annex: Examples of operational aspects of research reactors that require particular attention in a quality assurance programme.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/928
ISBN: 92-0-200293-2
Publication Date: 23-4-1993
This publication presents international consensus principles useful in the operation of a research reactor. lt is complemented by Safety Series No. 35-S1, Code on the Safety of Nuclear Research Reactors: Design. Both publications provide an overview on basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies. Contents: Definitions; 1. Introduction; 2. Safety objectives; 3. Regulatory supervision; 4. Responsibilities for safe operation; 5. Safety analysis for operation; 6. Operational limits and conditions; 7. Operating procedures; 8. Commissioning; 9. Maintenance, period testing and inspection; 10. Core management and fuel handling; 11. Records and reports; 12. Reactor utilization; 13. Modifications; 14. Radioactive wastes; 15. Radiation protection; 16. Emergency planning; 17. Security; 18. Quality assurance; 19. Decommissioning; Annex: Examples of operational aspects of research reactors that require particular attention in a quality assurance programme.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/928
ISBN: 92-0-104392-9
Publication Date: 14-1-1993
This publication presents international consensus principles useful in the operation of a research reactor. It is complemented by Safety Series No. 35-S1, Code on the Safety of Nuclear Research Reactors: Design. Both publications provide basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies. Contents: Definitions; 1. Introduction; 2. Safety objectives; 3. Regulatory supervision; 4. Responsibilities for safe operation; 5. Safety analysis for operation; 6. Operational limits and conditions; 7. Operating procedures; 8. Commissioning; 9. Maintenance, period testing and inspection; 10. Core management and fuel handling; 11. Records and reports; 12. Reactor utilization; 13. Modifications; 14. Radioactive wastes; 15. Radiation protection; 16. Emergency planning; 17. Security; 18. Quality assurance; 19. Decommissioning; Annex: Examples of operational aspects of research reactors that require particular attention in a quality assurance programme.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/931
ISBN: 92-0-101894-0
Publication Date: 10-8-1994
Proceedings of a symposium organized by the IAEA and hosted by the Korea Electric Power Corporation on behalf of the Government of the Republic of Korea, in co-operation with the CEC, the European Nuclear Society, the Korea Atomic Industrial Forum, the Korean Nuclear Society, the OECD/NEA and the World Energy Council, Seoul, 18-22 October 1993. The purpose of the symposium was to provide a forum for discussions on the need for nuclear power, on the features of advanced nuclear power systems and their design objectives and safety approaches, taking into consideration the views of regulatory bodies, on identifying barriers to the deployment of these systems, and on reviewing options for international co-operation. Contents: Opening session; Introduction and overviews of other relevant conferences; Design and safety objectives of advanced nuclear power systems; Panel: Regulatory experience and views on safety aspects of advanced reactors; Barriers and strategies for the deployment of advanced nuclear power systems; Panel: Evaluation of barriers and strategies for the deployment of advanced nuclear power systems; Options for international co-operation for the deployment of advanced nuclear power systems; Panel: The role of international organizations; Closing session.
Subject Classification: 0701 - Nuclear power planning and economics; 0703 - Reactor technology
STI/PUB/938
ISBN: 92-0-200593-1
Publication Date: 1-2-1994
This Safety Fundamentals publication presents an international consensus on the basic concepts underlying the principles for the regulation, management of safety and operation of nuclear installations. It forms a top level publication in the hierarchy of the IAEA Safety Series. In conjunction with this publication, Safety Standards and Safety Guides provide detailed requirements and recommendations for activities relating to siting, design, quality assurance, operation and regulation of nuclear installations. Contents: 1. Introduction; 2. Safety objectives; 3. Legislative and regulatory framework; 4. Management of safety; 5. Technical aspects of safety; 6. Verification of safety; Definitions; Annex: The concept of risk: Methods of risk evaluation and limitation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/938
ISBN: 92-0-300493-9
Publication Date: 9-12-1993
This Safety Fundamentals publication presents an international consensus on the basic concepts underlying the principles for the regulation, management of safety and operation of nuclear installations. It forms a top level publication in the hierarchy of the IAEA Safety Series. In conjunction with this publication, Safety Standards and Safety Guides provide detailed requirements and recommendations for activities relating to siting, design, quality assurance, operation and regulation of nuclear installations. Contents: 1. Introduction; 2. Safety objectives; 3. Legislative and regulatory framework; 4. Management of safety; 5. Technical aspects of safety; 6. Verification of safety; Definitions; Annex: The concept of risk: Methods of risk evaluation and limitation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/938
ISBN: 92-0-400693-5
Publication Date: 9-12-1993
This Safety Fundamentals publication presents an international consensus on the basic concepts underlying the principles for the regulation, management of safety and operation of nuclear installations. It forms a top level publication in the hierarchy of the IAEA Safety Series. In conjunction with this publication, Safety Standards and Safety Guides provide detailed requirements and recommendations for activities relating to siting, design, quality assurance, operation and regulation of nuclear installations. Contents: 1. Introduction; 2. Safety objectives; 3. Legislative and regulatory framework; 4. Management of safety; 5. Technical aspects of safety; 6. Verification of safety; Definitions; Annex: The concept of risk: Methods of risk evaluation and limitation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/938
ISBN: 92-0-101893-2
Publication Date: 19-7-1993
This Safety Fundamentals publication presents an international consensus on the basic concepts underlying the principles for the regulation, management of safety and operation of nuclear installations. It forms a top level publication in the hierarchy of the IAEA Safety Series. In conjunction with this publication, Safety Standards and Safety Guides provide detailed requirements and recommendations for activities relating to siting, design, quality assurance, operation and regulation of nuclear installations. Contents: 1. Introduction; 2. Safety objectives; 3. Legislative and regulatory framework; 4. Management of safety; 5. Technical aspects of safety; 6. Verification of safety; Definitions; Annex: The concept of risk: Methods of risk evaluation and limitation.
Subject Classification: 0603 - Nuclear power plants
STI/PUB/939
ISBN: 92-0-400493-2
Publication Date: 23-9-1993
Subject Classification: 0614 - Legal and governmental aspects
STI/PUB/939
ISBN: 92-0-102793-1
Publication Date: 23-9-1993
Subject Classification: 0614 - Legal and governmental aspects
STI/PUB/940
ISBN: 92-0-103493-8
Publication Date: 20-1-1994
Subject Classification: 0804 - Waste management
STI/PUB/946
ISBN: 92-0-100395-1
Publication Date: 31-3-1995
Proceedings of an international conference, Vienna, 5-8 September 1994. The purpose of the conference was to discuss the present and future importance of the nuclear power option as a source for energy based on proven, accepted, economically competitive and environmentally benign technologies. The safe and reliable operation of existing nuclear power plants, the demonstration of convincing solutions to the storage and disposal of radioactive waste, a predictable licensing process and supportive government policies are essential prerequisites to achieving a wider public acceptance of nuclear power, which presently is the most important factor deciding its future application. Contents: Plenary session; National and regional overviews; Learning from experience: I. Operation and maintenance; II. Construction, quality assurance and decommissioning; III. Improving performance; Issues affecting the nuclear power option: I. Public acceptance; II. Irradiated fuel and waste management; III. Safety; IV. Economics, environment and liability; Timely preparation: I. Providing resources; II. Government strategies; Panel discussion; Closing statements.
Subject Classification: 0700 - Nuclear power
STI/PUB/949
ISBN: 92-0-101695-6
Publication Date: 23-10-1995
Proceedings of a symposium jointly organized with OECD/NEA, Vienna, 10-14 October 1994. The purpose of the symposium was to provide an opportunity for the exchange of information on the state of the art and the prospects of spent fuel storage, to discuss the worldwide situation and the major factors influencing the national policies in this field, and to identify the most important directions that national efforts and international co-operation in this area should take. Contents: Spent fuel storage programmes; Spent fuel storage technology; Licensing and safety aspects of spent fuel storage; Closing session; Poster presentations. Contents: Spent fuel storage programmes; Spent fuel storage technology; Licensing and safety aspects of spent fuel storage; Closing session; Poster presentations.
Subject Classification: 0602 - Fuel fabrication and storage; 0803 - Spent fuel management
STI/PUB/950
ISBN: 92-0-101194-6
Publication Date: 9-6-1994
This Safety Guide, published under the IAEAs Radioactive Waste Safety Standards (RADWASS) programme, outlines various possibilities for the development of a classification system for radioactive wastes. It proposes a modified classification system with general quantitative boundaries and gives guidance for the development of quantitative classification systems. Contents: 1. Introduction; 2. Approaches to radioactive waste classification; 3. Proposal for a radioactive waste classification system; Annex: Origin and types of radioactive waste; Glossary.
Subject Classification: 0804 - Waste management
STI/PUB/951
ISBN: 92-0-103393-1
Publication Date: 16-12-1993
Subject Classification: 0702 - Nuclear power operations
STI/PUB/952
ISBN: 92-0-101294-2
Publication Date: 9-6-1994
This safety guide, published under the IAEAs Radioactive Waste Safety Standards (RADWASS) programme, defines the process to be used and guidelines to be considered in selecting sites for deep geological disposal of radioactive wastes. It also addresses the social, economic and environmental factors to be considered in site selection. All data needed for the application of the guidelines are also specified. Contents: 1. Introduction; 2. Safety approach; 3. The siting process; 4. Site selection guidelines and data needs; Glossary.
Subject Classification: 0611 - Radioactive waste management; 0804 - Waste management
STI/PUB/953
ISBN: 92-0-100394-3
Publication Date: 21-3-1994
The 1985 Edition of the IAEAs Regulations for the Safe Transport of Radioactive Material reinforced the requirement placed on competent authorities to establish compliance assurance programmes that aim at ensuring that the Regulations are met in practice. This book is intended to provide further guidance on developing and implementing compliance assurance programmes to be used by competent authorities. It should also be useful to those competent authorities with established programmes seeking greater harmony in the international implementation of the Regulations. Additionally, it should assist the users of the Regulations in their interactions with competent authorities. Contents: Section I. Introduction; Section II. Responsibilities and functions of the competent authority; Section III. Regulations and guides; Section IV. Compliance assurance; Section V. Approvals and approval certificates; Section VI. International co-operation between competent authorities concerning packages and shipments on foreign territory; Annex I: Example of the organization of a compliance assurance programme; Annex II: Information to be included in applications for approvals; Annex III: Examples of approval certificates issued by the competent authority; Annex IV: Model of competent authority procedures for auditing a quality assurance programme; Annex V: Example/model of a check list for auditing a quality assurance programme; Annex VI: Example/model of a check list for inspecting transport documentation; Annex VII: Example/ model of a check list for inspecting transport operations; Annex VIII: Example/model of a check list for inspecting package manufacture; Annex IX: Example/model of a check list for inspecting maintenance and servicing operations.
Subject Classification: 0606 - Transport of radioactive material
STI/PUB/958
ISBN: 92-0-103694-9
Publication Date: 25-11-1994
This publication provides guidance and gives detailed advice on methods and practical examples to develop quality assurance (QA) programmes for the safe transport of radioactive material. It further promotes a flexible approach to the development of a QA programme and may be used to prepare such a programme for a specific application by selection of appropriate features. Contents: 1. Introduction; 2. Development of a quality assurance programme; 3. Quality assurance standards; 4. Elements of a quality assurance programme; Appendix: Graded approach; Annex I: Two comparative examples of quality assurance programme development; Annex II: References to examples of quality assurance standards; Annex III: Example of a documented quality assurance programme description for an infrequent consignor; Annex IV: Example of a documented quality assurance programme description for an infrequent carrier; Annex V: Example of a document control procedure for a small organization; Annex VI: Example of a document control procedure for a complex organization; Annex VII: Example of an internal audit procedure in a small organization; Annex VIII: Example of a flask maintenance procedure in a complex organization; Annex IX: Examples of poor interface control.
Subject Classification: 0606 - Transport of radioactive material; 0613 - Quality management
STI/PUB/959
ISBN: 92-0-103096-7
Publication Date: 7-10-1996
Proceedings of an international conference, Paris, 24-28 October 1994. Upon a request by the IAEA, the Swedish Risk Academy commissioned a set of background papers on issues relating to the comprehension of radiation risk to serve as a scientific input for the conference. The papers cover topics of importance for risk assessment and for comprehending and communicating on radiation risk. Contents: (Vol. 2) Background papers prepared for the conference by IPSN; Poster presentations: Assessment of radiation exposure levels; Assessment of radiation health effects; Impact of radiation on the environment; Perception of radiation risk; Managing radiation risk; The nuclear weapons legacy; Cancer and leukaemia clusters; Radon in homes; Radioactive waste disposal and the environment; Chernobyl health effects.
Subject Classification: 0609 - Radiation protection
STI/PUB/959
ISBN: 92-0-102194-1
Publication Date: 10-8-1994
Proceedings of an international conference, Paris, 24-28 October 1994. Upon a request by the IAEA, the Swedish Risk Academy commissioned a set of background papers on issues relating to the comprehension of radiation risk to serve as a scientific input for the conference. The papers cover topics of importance for risk assessment and for comprehending and communicating on radiation risk. Contents: (Vol. 1) 1. Introduction; 2. Comprehending radiation risks; 3. The concept of probability; 4. Risk perception; 5. Interpreting epidemiological results; 6. Problems in radiation risk assessment; 7. Cause structure of global mortality; 8. Radiation levels; 9. Problems in risk comparisons; 10. Risk communication; 11. Risk and ethics.
Subject Classification: 0609 - Radiation protection
STI/PUB/960
ISBN: 92-0-104594-8
Publication Date: 19-12-1994
This Safety Guide, a companion document to Safety Series Nos 35-S1 and 35-S2, is part of a set of publications in the IAEA Safety Series dealing with all the important areas of research reactor safety which includes Safety Standards, Safety Guides and Safety Practices. This guide presents guidelines, approved by international consensus, for the preparation, review and assessment of the safety documentation (Safety Series No. 35-S1) and for the preparation of the Safety Analysis Report (SAR) (Safety Series No. 35-S2). In addition, it is most applicable during the design and construction stages of research reactors, as well as during relicensing or reassessment of already existing reactors. Contents: 1. Introduction; 2. Requirements for safety assessment in the licensing process for a research reactor; 3. Preparation of the safety analysis report; 4. Performance of the review and assessment; Appendix: Contents of a Safety Analysis Report; Annex I: Safety analysis approach and methods; Annex II: Examples of input parameters and initial conditions; Annex III: Examples of items to be considered in the reactor description; Annex IV: Typical sources of radioactive material or radiation fields in a research reactor.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/961
ISBN: 92-0-104694-4
Publication Date: 15-12-1994
This Safety Guide, part of a set of publications in the IAEA Safety Series dealing with all the important areas of research reactor safety which includes Safety Standards, Safety Guides and Safety Practices, develops the general concepts presented in Safety Series Nos 35-S1 and 35-S2 and should be read in conjunction with them. This Safety Guide presents guidelines for the safe utilization and modification of research reactors to ensure that these projects are implemented without undue risks to personnel, the public, the environment or the reactor. While the Safety Guide is most applicable to existing reactors, it is also recommended for use by organizations planning to put a new reactor into operation. Contents: 1. Introduction; 2. Organization and responsibilities; 3. Safety assessment, categorization and approval routes; 4. General and specific safety requirements for design; 5. Pre-implementation phase of a utilization or modification project; 6. Implementation phase of a utilization or modification project; 7. Post-implementation phase of a utilization or modification project; 8. Operational safety requirements for experiments; 9. Safety considerations in the handling, dismantling, post-irradiation examination and disposal of experimental devices; 10. Safety aspects of out-of-reactor installations; 11. Quality assurance of experiments and modifications; Annex I: Categorization criteria; Annex II: Justification of a project.
Subject Classification: 0305 - Research reactors and particle accelerators (applications); 0604 - Research reactors
STI/PUB/963
ISBN: 92-0-301596-5
Publication Date: 12-8-1996