USA
Status of GT-MHR with emphasis on the power conversion system
Neylan, A.J.; Silady, F.A. (General Atomics, San Diego, CA (United States)); Kohler,
B.P. (AlliedSignal, Tempe, AZ (United States)); Lomba, D. (GEC-Alsthom, Belfort (France)); Rose, R. (Mechanical Technology, Inc., Latham, NY (United States))
IAEA-TECDOC--899, pp:55-66
International co-operation in developing the GT-MHR
La Bar, M.P.; Simon, W.A. (General Atomics, San Diego, CA (United States))
IAEA-TECDOC--988, pp:59-71
Nuclear graphite development, operational problems, and resolution of these problems at the Hanford
production reactors
Morgan, W.C. (Pacific Northwest Lab., Richland, WA (United States))
IAEA-TECDOC--901, pp:69-77
Fort St. Vrain decommissioning project
Fisher, M. (Public Service Co. of Colorado, Denver, CO (United States))
IAEA-TECDOC--1043, pp:123-131
COMEDIE BD1 experiment: Fission product behaviour during depressurization transients
Gillet, R.; Brenet, D. (DTP/SECC, CEA/GRENOBLE, Grenoble (France)); Hanson, D.L.
(General Atomics, San Diego, CA (United States)); Kimball, O.F. (Oak Ridge National
Lab., TN (United States))
IAEA-TECDOC--899, pp:145-156
GT-MHR spent fuel storage disposal without processing
Kiryushin, A.I.; Kuzavkov, N.G.; Gushin,
Yu.L.; Sukharev, Yu.P. (OKBM, Nizhny
Novgorod (Russian Federation)); Chudin,
A.G. (Minatom, Moscow (Russian Federation)); Richards, M.; Shenoy, A.
(General Atomics, San diego, CA (United States))
IAEA-TECDOC--1043, pp:191-199
Key Differences in the Fabrication of U. S. and German TRISO-Coated Particle Fuel, and their Implications on Fuel Performance
D. A. Petti, J. Bongiorno, J. T. Maki and G. K. Miller, Idaho National Engineering and Environmental Laboratory, USA
HTR-2002, pp:1-7
Development of an Integrated Performance Model for TRISO-Coated Gas Reactor Particle Fuel
G. K. Miller, D. A. Petti and J. T. Maki, Idaho National Engineering and Environmental Laboratory, USA
HTR-2002, pp:1-6
Examination of the Potential for Diversion or Clandestine Dual Use of a Pebble-Bed reactor to produce Plutonium
A. Ougouag, W. K. Terry and H. D. Gougar, Idaho National Engineering and Environmental Laboratory, USA
HTR-2002, pp:1-6
Deep Burn Transmutation of Nuclear Waste
C. Rodriguez, A. Baxter and D. McEachern, General Atomics, Francesco Venneri, Los Alamos National Laboratory and General Atomics and D. Williams, Oak Ridge National Laboratory, USA
HTR-2002, pp:1-5
Matrix Formulation of Pebble Circulation in the PEBBED Code
H. D. Gougar, W. K. Terry and A. J. Ougouag, Idaho National Engineering and Environmental Laboratory, USA
HTR-2002, pp:1-6
Physics Studies for a Particle-Bed Gas Cooled Fast Reactor Core Design
T. A. Taiwo, M. Fatone, G. Palmiotti and R. N. Hill, Reactor Analysis and Engineering Division, Argonne National Laboratory, USA
HTR-2002, pp:1-5
Flow Distribution of Pebble Bed High Temperature Gas Cooled Reactors Using Large Eddy Simulation
Y.A Hassan and G. Gokhan Yesilut, Department of Nuclear Engineering, Texas A&M University, USA
HTR-2002, pp:1-6
Design of a Power Conversion System for an Indirect Cycle, Helium Cooled Pebble Bed Reactor System
C. Wang, R. G. Ballinger and P. W. Stahle, Department of Nuclear Engineering, Massachusetts Institute of Technology, USA
HTR-2002, pp:1-11
Studies on Air Ingress for Pebble Bed Reactors
R. L. Moore, C. H. Oh, B. J. Merrill and D. A. Petti, Idaho National Engineering and Environmental Laboratory, USA
HTR-2002, pp:1-5
Conceptual design of a passive, inherently safe emergency shutdown rod for High Temperature Reactor applications
A. M. Ougouag, W. K. Terry and R. R. Schultz, Idaho National Engineering and Environmental Laboratory, USA
HTR-2002, pp:1-6
Graphite Materials Testing in the ATR for Lifetime management of Magnox Reactors
S. B. Grover, Idaho National Engineering and Environmental Laboratory, USA and M. P. Metcalfe, British Nuclear Fuels plc, Research and Technology, Berkeley Centre, United Kingdom
HTR-2002, pp:1-7
MIT Modular Pebble Bed Reactor (MPBR)
Andrew C. Kadak, Ronald G. Ballinger, Institute of Technology, Massachusetts, USA
HTR-2004, pp:1-1
Advanced Coated Particle Fuel Options
J.M. Kendall, Global Virtual LLC, Prescott, Arizona, USA; R.E. Bullock, Sigma Science Inc. Albuquerque, New Mexico, USA
HTR-2004, pp:1-9
Current Capabilities of The Fuel Performance Modeling Code Parfume
G.K. Miller, J.T. Maki, D.L. Knudson, D.A. Petti, Idaho National Engineering and Environmental Laboratory, Idaho, USA
HTR-2004, pp:1-7
TIMCOAT: An Integrated Fuel Performancemodel For Coated Particle Fuel
Jing Wang, Ronald G. Ballinger, Heather J. Maclean, Jane T. Diecker, Department of Nuclear Engineering, Massachusetts Inst. of Technoogy, Cambridge, USA
HTR-2004, pp:1-45
Fracture Mechanics Based Coated Particle Fuel Failure Models
Jing Wang, Ronald G. Ballinger, MIT Nuclear Engineering Dept., Cambridge, USA
HTR-2004, pp:1-12
Design Optimization and Analysis of Coated Particle Fuel Using Advanced Fuel Performance Modeling Techniques
Jing Wang, Ronald G. Ballinger, Jane T. Diecker, MIT Nuclear Engineering Dept., Cambridge, USA
HTR-2004, pp:1-20
Silver Ion Implantation and Annealing In Cvd Silicon Carbide: The Effect of Temperature on Silver Migration
Heather J. MacLean, Ronald G. Ballinger, MIT, Cambridge, USA
HTR-2004, pp:1-20
Modular Helium Reactor Fuel Cycle Concepts and Sustainability
Chris Ellis, Alan Baxter, Arkal Shenoy, General Atomics, San Diego, California, USA
HTR-2004, pp:1-8
Program of GT-MHR Fuel Development and Justification
N. Kodochigov, Yu. Sukharev, OKBM, RUSSIA; N. Ponomarev-Stepnoy, Yu. Degaltsev, RCC KI, RUSSIA; V. Novikov, I. Kadarmetov, V. Makarov, VNIINM, RUSSIA; V. Sulaberidze NIIAR, RUSSIA; A. Chernikov, SPA Lutch, RUSSIA; D. Mc Eachern, R. Noren, GA, USA
HTR-2004, pp:1-9
The PBMR Steady State And Coupled Kinetics Core Thermal-Hydraulics Benchmark Test Problems
Frederik Reitsma, Gerhard Strydom, Reactor Analysis Group, PBMR (Pty) Ltd, SOUTH AFRICA; Han de Haas, D.F. da Cruz, Fuel, Actinides & Isotopes Group, NRG, THE NETHERLANDS; Kostadin Ivanov, Bismark Tyobeka, Nuclear Engineering Program, Penn State University, USA; Ramatsemela Mphahlele, Nuclear Engineering Program, Penn State University, USA and National Nuclear Regulator, Centurion, SOUTH AFRICA; Tom Downar, Volkan Seker, Nuclear Engineering Department, Purdue University, USA; Hans D. Gougar, Fission & Fusion Systems, INEEL, USA
HTR-2004, pp:1-19
Design of Pebble-Bed Reactors Using Genetic Algorithms
Hans D. Gougar, William K. Terry, Abderrafi M. Ougouag, Idaho National Engineering and Environmental Laboratory, Idaho, USA; Kostadin N. Ivanov, The Pennsylvania State University, Dept. of Mechanical and Nuclear Engineering, PA, USA
HTR-2004, pp:1-11
Advanced Modularity Design for The MIT Pebble Bed Reactor
Andrew C. Kadak, Marc. V. Berte (Graduate Student), Dept. of Nuclear Engineering, Massachusetts Institute of Technology, USA
HTR-2004, pp:1-16
Data For Computing Radiation Induced Damage In HTR Fuel Matrices
A.M. Ougouag , C.A. Wemple, Idaho National Engineering and Environmental Laboratory, Idaho, USA
HTR-2004, pp:1-8
Sensitivity Studies of Modular High-Temperature Gas-Cooled Reactor (MHTGR) Postulated Accidents
Sydney Ball, Oak Ridge National Laboratory, Oak Ridge, USA
HTR-2004, pp:1-13
Advanced High-Temperature Reactor (AHTR) Loss-Of-Forced-Circulation Accidents
Sydney Ball, Charles Forsberg, Nuclear Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, USA
HTR-2004, pp:1-9
Air Ingress Benchmarking with Computational Fluid Dynamics Analysis
Andrew C. Kadak, Tieliang Zhai (Graduate Student), Department of Nuclear Engineering, MIT Massachusetts, Massachusetts, USA
HTR-2004, pp:1-35
From Field to Factory - Taking Advantage of Shop Manufacturing for the Pebble Bed Modular Reactor
Edward Wallace, PBMR (Pty) Ltd, Centurion, SOUTH AFRICA; Regis Matzie, Westinghouse Electric Company LLC, USA; Roger Heider, Sargent and Lundy, LLC, USA; John Maddalena, Imhotep Consulting, CC, SOUTH AFRICA
HTR-2004, pp:1-18
Pebble Flow Experiments For Pebble Bed Reactors
Andrew C. Kadak, Department of Nuclear Engineering, Massachusetts Institute of Technology; Martin Z. Bazant, Department of Mathematics, Massachusetts Institute of Technology
HTR-2004, pp:1-25
Comparison of predicted and measured fission product
behaviour in the Fort St. Vrain HTGR during the first three
cycles of operation
Hanson, D.L.; Jovanovic, V.; Burnette, R.D. (GA
Technologies Inc., San Diego, CA (United
States))
IWGGCR--13, pp:2-14
Operational experience at Fort St. Vrain
Bramblett, G.C.; Fisher, C.R.; Swart, F.E. (General Atomic Co., San Diego, CA (USA))
IWGGCR--1, pp:6-10
Utility/user requirements for the modular high temperature
gas-cooled reactor
Boyer, V.S.; Kendall, J.M.; Gotschall, H.L. (Gas-Cooled
Reactor Associates, San Diego, CA (USA))
IWGGCR--19, pp:9-13
Scale model study of the seismic response of a nuclear reactor core
Dove, R.C.; Dunwoody, W.E.; Rhorer, R.L. (Los Alamos National Lab., NM)
IWGGCR--6, pp:13-32
Fuel irradiation experiments on HFR-K6 and HFR-B1 with intermittent water vapour injections
Nabielek, H. (Forschungszentrum Juelich GmbH (Germany)); Conrad, R. (Joint Research
Centre, Petten (Netherlands)); Roellig, K. (ABB Kraftwerke AG, Mannheim (Germany)); Meyers, B.F. (Oak Ridge National Lab., TN (United States))
IAEA-TECDOC--784, pp:17-24
Utility/user requirements for the MHTGR desalination plant
Brown, S.J. (Gas-Cooled Reactor Associates, San Diego, CA
(USA)); Snyder, G.M. (Metropolitan Water District of Southern
California, Los Angeles, CA (USA))
IWGGCR--19, pp:17-23
HTGR programme in the United States of America
Fox, J.E. (USDOE, Washington, DC (United States))
IWGGCR--25, pp:21-22
Development History of the Gas Turbine Modular High Temperature Reactor
H.L. Brey, Consultant to EPRI
IAEA-TECDOC--1238, pp:25-49
Fort St. Vrain circulator operating experience
Brey, H.L. (Public Service Co. of Colorado, Denver (USA))
IWGGCR--17, pp:31-38
Design and application for a high-temperature nuclear heat source
Quade, R.N. (General Atomic Co., San Diego, CA (USA))
IWGHTR--6, pp:31-45
Technical and economic prospects for the gas-turbine MHTGR
Mears, L.D.; Penfield, S.R. Jr. (Gas-Cooled Reactor Associates, San Diego, CA (United States))
IAEA-TECDOC--761, pp:33-41
Design requirements for high temperature metallic component materials in the US modular
HTGR
Shenoy, A.S.; Betts, W.S. (General Atomics, San Diego, CA (USA))
IWGGCR--18, pp:33-41
HTGR core seismic analysis using an array processor
Shatoff, H.; Charman, C.M. (General Atomic Co., San Diego, CA)
IWGGCR--6, pp:33-59
The analysis and evaluation of recent operational experience from the Fort St. Vrain HTGR
Moses, D.L. (Oak Ridge National Lab., TN (USA)); Lanning, W.D. (Nuclear
Regulatory Commission, Washington, DC (USA). Office for Analysis and
Evaluation of Operational Data)
IAEA-TECDOC--358, pp:35-45
Bases for the MHTGR source term and containment concepts
Williams, P.M. (USDOE, Washington, DC (United States))
IAEA-TECDOC--757, pp:41-46
HTGR fuel element structural design consideration
Alloway, R.; Gorholt, W.; Ho, F.; Vollman, R.; Yu, H. (GA Technologies, Inc., San Diego, CA (USA))
IWGGCR--11, pp:43-57
A microstructurally based fracture model for nuclear graphite
Burchell, T.D. (Oak Ridge National Lab., TN (United States))
IAEA-TECDOC--690, pp:49-58
Fission product behaviour in the Peach Bottom and Fort St. Vrain HTGRs
Hanson, D.L.; Baldwin, N.L.; Strong, D.E. (General Atomic Co., San Diego, CA (USA))
IWGGCR--2, pp:49-54
Experimental results of air ingress in heated graphite channels: A summary of American analyses of the Windscale and Chernobyl accidents
Schweitzer, D.G. (Brookhaven National Lab., Upton, NY (United States))
IAEA-TECDOC--784, pp:50-54
Gas-cooled fast reactor safety - and overview and status of the U.S. program
Torri, A.; Buttemer, D.R. (General Atomic Co., San Diego, CA (USA))
IWGGCR--1, pp:51-57
Distribution of the decay heat in various module HTRs and influence on peak fuel temperatures
Teuchert, E.; Haas, K.A.; Heek, A. van (Forschungszentrum Juelich GmbH
(Germany)); Kasten, P.R. (Tennessee Univ., Knoxville, TN (United States))
IAEA-TECDOC--757, pp:53-62
Fort Saint Vrain operational experience
Fuller, C.H. (Public Service Co. of Colorado, Denver, CO
(USA))
IWGGCR--19, pp:55-61
Iodine sorption and desorption from low-alloy steel and graphite
Wichner, R.P.; Osborne, M.F.; Lorenz, R.A.; Briggs, R.B. (Oak Ridge National Lab., TN (USA))
IWGGCR--2, pp:55-64
Personnel radiation exposure in HTGR plants
Su, S.; Engholm, B.A. (General Atomic Co., San Diego, CA (USA))
IWGGCR--1, pp:57-62
Operating experience with gas-bearing circulators in a high-pressure helium loop
Sanders, J.P.; Gat, U.; Young, H.C. (Oak Ridge National Lab., TN (USA). Engineering Technology Div.)
IWGGCR--17, pp:59-65
Seismic design, analysis and testing of the HTGR MK-IVA steam generator
Orr, J.D.; Schleicher, R.W.; Tong, K.J. (General Atomic Co., San Diego, CA)
IWGGCR--6, pp:61-74
The Gulf General Atomic gas-cooled fast breeder reactor system
Fortescue, P
IAEA-TECDOC--154, pp:62-77
Thermal stability and environmental compatibility of Inconel 617
Kimball, O.F. (Oak Ridge National Lab., Oak Ridge, TN (USA). Metals and
Ceramics Div.)
IWGGCR--18, pp:62-69
Developmental assessment of the Fort St. Vrain version of the composite HTGR analysis program (CHAP-2)
Stroh, K.R. (Los Alamos Scientific Lab., NM (USA))
IWGGCR--1, pp:63-67
The statistical characterization of tensile strengths for a nuclear-type graphite
Kennedy, C.R.; Eatherly, W.P. (Oak Ridge National Lab., TN (USA))
IWGGCR--11, pp:63-68
Spatial variability in the tensile strength of an extruded nuclear-grade graphite
Strizak, J.P. (Oak Ridge National Lab., TN (United States))
IAEA-TECDOC--690, pp:64-69
Probabilistic risk assessment of HTGRs
Fleming, K.N.; Houghton, W.J.; Hannaman, G.W.; Joksimovic, V. (General Atomic Co., San Diego, CA (USA))
IWGGCR--1, pp:68-72
Modular high temperature gas-cooled reactor heat source for coal conversion
Schleicher, R.W. Jr.; Lewis, A.C. (General Atomics, San Diego, CA (United States))
IAEA-TECDOC--761, pp:69-75
Strength of irradiated graphite: A review
Price, R.J. (General Atomic Co., San Diego, CA (USA))
IWGHTR--3, pp:69-76
Technology development for the modular high-temperature
gas-cooled reactor
Homan, F.J. (Oak Ridge National Lab., TN (USA)); Turner,
R.F. (General Atomics, San Diego, CA (USA))
IWGGCR--19, pp:71-79
ORNL analyses of AVR performance and safety
Cleveland, J.C. (Oak Ridge National Lab., TN (USA))
IAEA-TECDOC--358, pp:73-84
Passive decay and residual heat removal in the MHTGR
Dilling, D.A.; Ghose, S.K.; Berkoe, J.M. (Bechtel National, Inc., San
Francisco, CA (United States)); Caspersson, S.A. (ABB/Combustion
Engineering, Inc., Windsor, CT (United States)); Bramblett, G.C. (General
Atomics, San Diego, CA (United States))
IAEA-TECDOC--757, pp:75-82
Derivation of criteria for primary circuit activity in an HTGR
Su, S.D.; Barsell, A.W. (General Atomic Co., San Diego, CA (USA))
IWGGCR--2, pp:75-80
Seismic qualification using digital signal processing/modal testing and finite element techniques
Steedman, J.B. (NTS, Fullerton, CA); Edelstein, A
IWGGCR--6, pp:75-117
Pyrolysis and its potential use in nuclear graphite disposal
J.B. Mason, D. Bradbury
TCM-Manchester99, pp:77-84
Seismic analysis of the modular high temperature gas cooled
reactor
Tajirian, F.F.; Longstreth, M.; Appleford, A. (Bechtel National,
Inc., San Francisco, CA (USA))
IWGGCR--22, pp:78-85
The approach to multimodule control of the MHTGR
Woodworth, C.M. (Stone and Webster Engineering Corp.,
Boston, MA (USA)); Rodriguez, C. (General Atomics, San
Diego, CA (USA)); Starr, T.M. (Combustion Engineering, Inc.,
Chattanooga, TN (USA))
IWGGCR--19, pp:80-85
Impact of increasing MHTGR power on passive heat removal
Dunn, T.D.; Schwartz, A.A.; Silady, F.A. (General Atomics, San Diego, CA
(United States))
IAEA-TECDOC--757, pp:83-89
MHTGR radionuclide source terms for use in siting
Inamati, S.B.; Neylan, A.J.; Silady, F.A. (General Atomics, San Diego, CA (United States)); Walker, L.L. (SWEC, United States (United States))
IAEA-TC--389.26, pp:83-93
Systems engineering requirements impacting MHTGR circulator design
Chi, H.W.; Baccaglini, G.M.; Potter, R.C.; Shenoy, A.S. (GA Technologies, Inc., San Diego, CA (USA))
IWGGCR--17, pp:83-93
Automated differentiation of computer models for sensitivity
analysis.
Worley, B.A. (Oak Ridge National Lab., TN (USA))
IWGGCR--24, pp:86-92
Helium circulator design concepts for the modular high temperature gas-cooled reactor (MHTGR) plant
McDonald, C.F.; Nichols, M.K.; Kaufman, J.S. (GA Technologies, Inc., San Diego, CA (USA))
IWGGCR--17, pp:93-115
Safety research on iodine plate-out during postulated HTGR core heat up events
Barsell, A.W.; Chawla, O.P.; Hoot, C.G. (General Atomic Co., San Diego, CA (USA))
IWGGCR--2, pp:94-99
Analytical and experimental investigations of the passive heat transport in HTRs under severe
accident conditions
Rehm, W.; Barthels, H.; Jahn, W. (Forschungszentrum Juelich GmbH
(Germany)); Cleveland, J. (Oak Ridge National Lab., TN (United States));
Ishihara, M. (Japan Atomic Energy Research Inst., Ibaraki (Japan))
IAEA-TECDOC--757, pp:95-103
A review of reactor physics uncertainties and validation
requirements for the modular high-temperature gas-cooled
reactor.
Baxter, A.M.; Lane, R.K.; Hettergott, E.; Lefler, W. (General
Atomics, San Diego, CA (USA)).
IWGGCR--24, pp:104-111
Modeling and analysis of heat transfer from the MHTGR core through a steel reactor vessel to
the reactor cavity cooling system
Dilling, D.A.; Berkoe, J.M.; Ghose, S.K. (Bechtel National, Inc., San Franciso,
CA (United States)); Dunn, T.D. (General Atomics, San Diego, CA (United
States)); Caspersson, S.A. (ABB/Combustion Engineering, Inc., Windsor, CT
(United States))
IAEA-TECDOC--757, pp:111-116
Preliminary safety assessment of the 450 MWT MHTGR
Dunn, T.D.; Datta, K.; Hoot, C. (General Atomics, San Diego,
CA (United States))
IWGGCR--25, pp:111-116
Helium compressor aerodynamic design considerations for MHTGR circulators
McDonald, C.F. (GA Technologies, Inc., San Diego, CA (USA))
IWGGCR--17, pp:115-130
HTGR safety research program
Barsell, A.W.; Olsen, B.E.; Silady, F.A. (General Atomic Co., San Diego, CA (USA))
IWGGCR--1, pp:118-123
Quantitative HTGR safety and forced outage goals
Houghton, W.J.; Parme, L.L.; Silady, F.A. (GA Technologies, Inc., San Diego,
CA (USA))
IAEA-TECDOC--358, pp:121-129
Primary coolant chemistry of the Peach Bottom and Fort St. Vrain high temperature gas-cooled reactors
Burnette, R.D.; Baldwin, N.L. (General Atomic Co., San Diego, CA (USA))
IWGGCR--2, pp:132-137
Fission product retention in TRISO coated UO2 particle fuels
subjected to HTR simulated core heating tests
Baldwin, C.A.; Kania, M.J. (Oak Ridge National Lab., TN
(United States))
IWGGCR--25, pp:132-138
Fission-gas release during hydrolysis of exposed fuel kernels.
Richards, M.B.; Hanson, D.L.; Turner, R.F. (General Atomics,
San Diego, CA (United States))
IWGGCR--25, pp:139-143
Effect of water vapor on the release of fission gases from UCO
in HTGR coated fuel particles.
Myers, B.F. (Oak Ridge National Lab., TN (United States))
IWGGCR--25, pp:143-151
Development and test evaluation of duplex steam reformer tube
Allen, D.C.; Meyer, D.J.; Pflasterer, G.R. (General Electric Co., Sunnyvale, CA (USA))
IWGHTR--6, pp:151-163
HTR fuel: prediction of fission product release in accidents
Nabielek, H.; Verfondern, K. (KFA Juelich
(Germany)); Goodin, D.T. (GA Technologies
(United States))
IWGGCR--13, pp:155-169
Gas erosion of impeller housing in the operation of a high-temperature, high-pressure helium circulator
Sanders, J.P.; Heestand, R.L.; Young, H.C. (Oak Ridge National Lab., TN (USA))
IWGGCR--17, pp:156-163
The licensing experience of the modular high-temperature
gas-cooled reactor (MHTGR)
Silady, F.A. (General Atomics, San Diego, CA (USA)); Cunliffe,
J.C. (Bechtel National, Inc., San Francisco, CA (USA));
Walker, L.P. (Stone and Webster Engineering Corp., Boston,
MA (USA))
IWGGCR--19, pp:156-163
Preliminary risk assessments of the small HTGR
Everline, C.J.; Bellis, E.A. (GA Technologies, Inc., San Diego, CA (USA))
IAEA-TECDOC--358, pp:157-164
In-pile corrosion of grade H-451 graphite by steam.
Richards, M.B.; Gillespie, A.G.; Hanson, D.L. (General
Atomics, San Diego, CA (United States))
IWGGCR--25, pp:157-162
Study of seismic design bases for nuclear power plants in the US
Kintzer, F.C. (International Engineering Co., Inc., Berkeley, CA); Yanev, P.I.; Gotschall, H.L
IWGGCR--6, pp:161-181
Status of MHTGR steam generator design in the United States of America
Spring, A.H. (Combustion Engineering Inc., Chattanooga, TN (United States))
IWGGCR--15, pp:171-175
Environmental aspects of MHTGR operation
Neylan, A.J. (General Atomics, San Diego, CA (USA)); Dilling,
D.A. (Bechtel National, Inc., San Francisco, CA (USA));
Cardito, J.M. (Stone and Webster Engineering Corp., Boston,
MA (USA))
IWGGCR--19, pp:176-182
Licensing of HTGRs in the United States
Fisher, C.R.; Orvis, D.D. (General Atomic Co., San Diego, CA (USA))
IWGGCR--1, pp:184-190
Auxiliary Bearing Design Considerations for Gas-Cooled Reactors
S.R. Penfield Jr., E. Rodwell, Technology Insights, EPRI
9 Overlook Lane, 3412 Hillview Ave
Carthage, TN 37030 USA, Palo Alto, CA 94303 USA
IAEA-TECDOC--1238, pp:190-201
Gaseous and metallic fission product transport characteristics of a modular pebble bed HTGR
during loss of core cooling accidents
Inamati, S.B.; Richards, M.B.; Hoot, C.G. (GA Technologies, Inc., San Diego,
CA (USA))
IAEA-TECDOC--358, pp:195-202
HTGR safety philosophy
Joksimovic, V.; Fisher, C.R. (General Atomic Co., San Diego, CA (USA))
IWGGCR--1, pp:207-213
Effect of foundation embedment on the seismic response of a high-temperature gas-cooled reactor plant
Lee, T.H.; Thompson, R.W.; Charman, C.M. (General Atomic Co., San Diego, CA)
IWGGCR--6, pp:207-236
The effect of volume on the tensile strength of several nuclear-grade graphites
Strizak, J.P. (Oak Ridge National Lab., TN (United States))
IAEA-TECDOC--690, pp:233-241
The effects of specimen geometry and size on the fracture toughness of nuclear graphites
Romanoski, G.R.; Burchell, T.D. (Oak Ridge National Lab., TN (United States))
IAEA-TECDOC--690, pp:241-248
Modular helium reactor for non-electric applications
Shenoy, A. (General Atomics, San Diego, CA (United States). Systems
Engineering)
IAEA-TECDOC--923, pp:253-277
The effect of inlet and outlet shell-side flow and heat transfer on the performance of HTGR straight tube heat exchangers
Carosella, D.P. (GA Technologies Inc., San Diego, California
(United States))
IWGGCR--9, pp:266-275
Simulation of thermal response of the 250 MWT modular HTGR during hypothetical
uncontrolled heat up accidents
Harrington, R.M.; Ball, S.J. (Oak Ridge National Lab., TN (USA))
IAEA-TECDOC--358, pp:273-282
Graphite surveillance in N Reactor
Woodruff, E.M. (Westinghouse Hanford Co., Richland, WA (United States). N Reactor
Facility and Operation Assurance)
IAEA-TECDOC--690, pp:273-280
Status of a reformer design for a modular HTGR in an in-line configuration
Gluck, R. (General Electric Co., Advance Reactors Systems
Dept., California (United States)); Whitling, W.H.; Lipps, A.J
IWGGCR--9, pp:276-287
Pressure vessel design codes: A review of their applicability to HTGR components at temperatures above 800 deg C
Hughes, P.T. (General Electric Co., Sunnyvale, CA (United
States)); Over, H.H. (Kernforschungsanlage Juelich GmbH,
IRW, Juelich (Germany)); Bieniussa, K. (Gesellschaft fuer
Reaktorsicherheit mbH, Koeln (Germany))
IWGGCR--9, pp:335-344
ORNL's NRC-sponsored HTGR safety and licensing analysis activities for Fort St. Vrain and
advanced reactors
Ball, S.J.; Cleveland, J.C.; Harrington, R.M. (Oak Ridge National Lab., TN
(USA))
IAEA-TECDOC--358, pp:337-344
Status of design code work for metallic high temperature components
Bieniussa, K. (Gesellschaft fuer Reaktorsicherheit mbH, Koeln
(Germany)); Seehafer, H.J. (INTERATOM, Bergisch Gladbach
(Germany)); Over, H.H. (Kernforschungsanlage Juelich, IRW,
Juelich (Germany)); Hughes, P. (General Electric Co., CA
(United States))
IWGGCR--9, pp:345-362
The effect of creep-fatigue damage relationships upon HTGR heat exchanger design
Kozina, M.M.; King, J.H. (GA Technologies Inc., San Diego,
CA (United States)); Basol, M. (Combustion Engineering Inc.,
Tennessee (United States))
IWGGCR--9, pp:377-388
The design status of the United States Department of Energy modular high temperature gas cooled reactor
Mills, Raymond R. Jr. (Modular High Temperature Gas Cooled Reactor Plant Design Control Office (United States))
IAEA-TC--389.26, pp:389-394
An economic assessment of the U.S. MHTGR design
Mears, L.D. (Gas-Cooled Reactor Associates, San Diego, CA (USA))
IAEA-TC--389.26, pp:421-449
Present status of MHTGR program in USA
Millunzi, A. (comp.) MHTGR Program Team
IAEA-TC--389.26, pp:618-633
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