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Volume 91

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Number 1

Table of Contents
Authors(Emil E. Leitz, Yoshiyuki Kataoka, Hiroaki Suzuki, Sigeo Hatamiya, Michio Murase, Isao Sumida, Tetsuo Horiuchi, Minoru Miki, Yoshiro Asahi, Ichiro Sugawara, Toshiki Kobayashi, T. C. Hung, V. K. Dhir, Dong H. Nguyen, Brett J. Menaker, Russell E. Allen, Harry E. Painter, Kåre Hannerz, Lars Nilsson, Tor Pedersen, Christen Pind, Stanley Rosen, Richard D. Ivany, John F. Kapinos, Suk K. Sim, Howard J. Bruschi, Ronald P. Vijuk, Stanley H. Levinson, Robert S. Enzinna, Selim Sancaktar, T. van de Venne, Robert M. Kemper, Christine M. Vertes, John J. Taylor, Karl E. Stahlkopf)
Preface Safety of Next Generation Power Reactors(Alan E. Waltar)

Next-Generation Power Reactor Information System

Emil E. Leitz

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 11-15

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34437

Conceptual Design and Safety Characteristics of a Natural-Circulation Boiling Water reactor

Yoshiyuki Kataoka, Hiroaki Suzuki, Sigeo Hatamiya, Michio Murase, Isao Sumida, Tetsuo Horiuchi, Minoru Miki

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 16-27

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34438

Conceptual Design of the Integrated Reactor with Inherent Safety

Yoshiro Asahi, Ichiro Sugawara, Toshiki Kobayashi

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 28-50

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34439

Decay Heat Removal in the Sodium Advanced Fast Reactor with the MDSNP Code

T. C. Hung, V. K. Dhir

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 51-60

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34440

Role of Feedback Reactivities in the Passive Safety of Nuclear Reactors: The Case of the Fast Flux Test Facility

Dong H. Nguyen

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 61-74

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34441

Passive Containment Cooling for an Advanced Small Pressurized Water Reactor

Brett J. Menaker, Russell E. Allen, Harry E. Painter

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 75-80

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Safety / dx.doi.org/10.13182/NT90-A34442

The PIUS Pressurized Water Reactor: Aspects of Plant Operation and Availability

Kåre Hannerz, Lars Nilsson, Tor Pedersen, Christen Pind

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 81-88

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Safety / dx.doi.org/10.13182/NT90-A34443

Loss-of-Coolant Accident Aspects of the Combustion Engineering Advanced Light Water Reactor—System 80+

Stanley Rosen, Richard D. Ivany, John F. Kapinos, Suk K. Sim

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 89-94

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Safety / dx.doi.org/10.13182/NT90-A34444

Safety: Evolving Technologies for Tomorrow’s Power Reactors

Howard J. Bruschi, Ronald P. Vijuk

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 95-101

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Safety / dx.doi.org/10.13182/NT90-A34445

Probabilistic Analysis for Conceptual Design of the Babcock & Wilcox Advanced Light Water Reactor

Stanley H. Levinson, Robert S. Enzinna, B&W Nuclear Service Company, P.O. Box 10935, Lynchburg, Virginia 24506-0935

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 102-111

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Safety / dx.doi.org/10.13182/NT90-A34446

Probabilistic Risk Assessment Insights from New Westinghouse Pressurized Water Reactor Designs Studied in 1982–1987

Selim Sancaktar, T. van de Venne

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 112-117

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Safety / dx.doi.org/10.13182/NT90-A34447

Loss-of-Coolant Accident Performance of the Westinghouse 600-MW(electric) Advanced Pressurized Water Reactor

Robert M. Kemper, Christine M. Vertes

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 118-128

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Safety / dx.doi.org/10.13182/NT90-A34448

Nuclear Power — A Path to the Future

John J. Taylor, Karl E. Stahlkopf, Electric Power Research Institute, 3412 Hillview Avenue, P.O. Box 10412, Palo Alto, California 94303

Nuclear Technology / Volume 91 / Number 1 / July 1990 / Pages 129-132

Technical Paper / Safety of Next Generation Power Reactor / Economic / dx.doi.org/10.13182/NT90-A34449

Number 2

Table of Contents
Authors(David Meneghetti, Dwight A. Kucera, Siegfried Jacobi, Wolfgang Kröger, Rudolf Schulten, Gregory J. Van Tuyle, Gregory C. Slovik, Robert J. Kennett, Bing C. Chan, Arnold L. Aronson, Gregory J. Van Tuyle, Peter Kroeger, Gregory C. Slovik, Bing C. Chan, Robert J. Kennett, Arnold L. Aronson, Robert T. Lancet, Robert Z. Litwin, Ravnesh C. Amar, Robert D. Rogers, Alan V. von Arx, Charles J. Mueller, David C. Wade, Charles J. Mueller, James E. Cahalan, David J. Hill, John M. Kramer, John F. Marchaterre, Dean R. Pedersen, Roger W. Tilbrook, T. Y. C. Wei, Arthur E. Wright, Karl Verfondern, Werner Schenk, Heinz Nabielek, John Cleveland, Daniel E. Carroll, Kenneth D. Bergeron, Werner Scholtyssek, Greg D. Valdez, Richard Gido)

Reactivity Feedback Components of a Homogeneous U10Zr-Fueled 900-MW(thermal) Liquid-Metal Reactor

David Meneghetti, Dwight A. Kucera

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 139-145

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34423

Failed Fuel Surveillance During in-Vessel Fuel Storage in Fast Breeder Reactors

Siegfried Jacobi

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 146-153

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34424

Technology and Safety Aspects of the German High-Temperature Gas-Cooled Reactor

Wolfgang Kröger, Rudolf Schulten

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 154-164

Technical Paper / Safety of Next Generation Power Reactor / Fission Reactor / dx.doi.org/10.13182/NT90-A34425

Analyses of Unscrammed Events Postulated for the Prism Design

Gregory J. Van Tuyle, Gregory C. Slovik, Robert J. Kennett, Bing C. Chan, Arnold L. Aronson

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 165-184

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34426

Examining the Inherent Safety of Prism, Safr, and the Mhtgr

Gregory J. Van Tuyle, Peter Kroeger, Gregory C. Slovik, Bing C. Chan, Robert J. Kennett, Arnold L. Aronson

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 185-202

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34427

Safety and Licensing of Safr-An Advanced Liquid-Metal Reactor

Robert T. Lancet, Robert Z. Litwin, Ravnesh C. Amar, Robert D. Rogers, Alan V. von Arx

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 203-214

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34428

Probabilistic Evaluation of Successful Inherent Shutdown in Unprotected Accidents in Innovative Liquid-Metal Reactors

Charles J. Mueller, David C. Wade

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 215-225

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34429

Risk Characterization of Safety Research Areas for Integral Fast Reactor Program Planning

Charles J. Mueller, James E. Cahalan, David J. Hill, John M. Kramer, John F. Marchaterre, Dean R. Pedersen, Roger W. Tilbrook, T. Y. C. Wei, Arthur E. Wright

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 226-234

Technical Paper / Safety of Next Generation Power Reactor / Nuclear Saftey / dx.doi.org/10.13182/NT90-A34430

Passive Safety Characteristics of Fuel for a Modular High-Temperature Reactor and Fuel Performance Modeling Under Accident Conditions

Karl Verfondern, Werner Schenk, Heinz Nabielek

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 235-246

Technical Paper / Safety of Next Generation Power Reactor / Fuel Cycle / dx.doi.org/10.13182/NT90-A34431

Modular High-Temperature Gas-Cooled Reactor Short-Term Thermal Response to Flow and Reactivity Transients

John Cleveland

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 247-258

Technical Paper / Safety of Next Generation Power Reactor / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34432

Liquid-Metal Reactor Applications of the Contain Code

Daniel E. Carroll, Kenneth D. Bergeron, Werner Scholtyssek, Greg D. Valdez, Richard Gido+

Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 259-267

Technical Paper / Safety of Next Generation Power Reactor / Technique / dx.doi.org/10.13182/NT90-A34433

Number 3

Table of Contents
Authors(Christoph Homann, Maurizio Bottoni, Burkhardt Dorr, Dankward Struwe, Tien-Ko Wang, Jun Hsin, Min Lee, Robert P. Martin, Bahram Nassersharif, Hideo Ezure, Masatoshi Nakagawa, Yasusi Tsuboi, Samim Anghaie, Larry L. Humphries, Nils J. Diaz, V. S. Iyer, S. K. Mukerjee, R. V. Kamat, K. T. Pillai, N. Kumar, V. N. Vaidya, D. D. Sood, Jeffrey W. Ray, Albert B. Reynolds, T. X. Bruce Qu, Thomas E. Blue, C. K. Chris Wang, Reinhard A. Gahbauer, Tien-Ko Wang, Liang-Chen Shiao, Chia-Lian Tseng)
Understanding Process Integration II(D. William Tedder)
Radioactivity and Health, A History(Hugh F. Henry)

Two-Dimensional Thermal-Hydraulic Calculations for the Mol 7C Experiments with the Computer Code BACCHUS

Christoph Homann, Maurizio Bottoni, Burkhardt Dorr, Dankward Struwe

Nuclear Technology / Volume 91 / Number 3 / September 1990 / Pages 275-286

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34452

A Study on Hydrogen Generation, Burning, and Their Impact on Fission Product Release Under a Postulated Large-Break LOCA

Tien-Ko Wang, Jun Hsin, Min Lee

Nuclear Technology / Volume 91 / Number 3 / September 1990 / Pages 287-296

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34453

A Best-Estimate Paradigm for Diagnosis of Multiple Failure Transients in Nuclear Power Plants Using Artificial Intelligence

Robert P. Martin, Bahram Nassersharif

Nuclear Technology / Volume 91 / Number 3 / September 1990 / Pages 297-310

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34454