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Number 1

Table of Contents
Comments on “Operating Margin of Soviet RBMK-1000 Nuclear Power Reactors” (E. Adamov, S. Kuznetsov, Yu. Nikitin, Yu. Cherkashov)
Response to “Comments on ‘Operating Margin of Soviet RBMK-1000 Nuclear Power Reactors’” (James M. Adams)

A Study of the Structural Integrity of the Core Support Structure of a Fast Breeder Reactor
Masahiro Ueta, Masakazu Ichimiya, Hiroshi Hirayama, Masayuki Asano, Hisaaki Ikeuchi, Katsuhisa Sekine, Tetsuhiko Kodama, Kenichiro Sato
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 1-12
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34749
Operational Margin Monitoring System for Boiling Water Reactor Power Plants
Shigeki Fukutomi, Yukio Takigawa, Hideaki Namba
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 13-24
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34750
Evaluation of the Loss of Residual Heat Removal Systems in Pressurized Water Reactors with U-Tube Steam Generators
Leonard W. Ward
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 25-38
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34751
A Long-Term MAAP 3.0B Analysis of a Severe Anticipated Transient Without Scram Accident in a Boiling Water Reactor
Min Lee, Ein-Chun Wu
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 39-51
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34752
Experiments to Investigate the Effect of Flight Path on Direct Containment Heating
Michael D. Allen, Martin M. Pilch, Richard O. Griffith, Robert T. Nichols
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 52-69
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34753
A New Pipe Wall Thinning Inspection System
Houlung Lee*, Edward S. Kenney
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 70-78
Technical Paper | Material | doi.org/10.13182/NT92-A34754
A Comparison of the BUGLE-80, SAILOR, and ELXSIR Neutron Cross-Section Libraries for PWR Pressure Vessel Surveillance Dosimetry and Shielding Applications
Hassan S. Basha, Michael P. Manahan, Sr.
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 79-96
Technical Paper | Material | doi.org/10.13182/NT92-A34755
Identification of Flow Patterns by Neutron Noise Analysis During Actual Coolant Boiling in Thin Rectangular Channels
Robert Kozma, Hugo van Dam, J. Eduard Hoogenboom
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 97-110
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34756
A Study of RELAP5/MOD2 and RELAP5/MOD3 Predictions of a Small-Break Loss-of-Coolant Accident Simulation Conducted at the ROSA-IV Large-Scale Test Facility
Sandra M. Sloan, Yassin Hassan
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 111-124
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34757
Fuzzy Logic Control of Steam Generator Water Level in Pressurized Water Reactors
Cheng Chung Kuan, Chaung Lin, Chang Chia Hsu
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 125-134
Technical Paper | Reactor Operation | doi.org/10.13182/NT92-A34758
A Numerical Performance Study of the PGCR Method Applied to Nuclear Reactor Heat Transfer Calculations
Paul E. Murray
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 135-140
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34759

Number 2

Table of Contents
Overview of 1990–1991 RETRAN Activities (Lance J. Agee)

Application of Statistical Combination of Uncertainties to the Three Mile Island Unit 1 Flux/Flow Reactor Trip Setpoint
Tae Y. Byoun, Ardesar A. Irani, John D. Luoma, Ronald E. Engel, Kenneth J. Doran, Govinda S. Srikantiah
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 152-161
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34738
A Nondiffusive Solution Method for RETRAN-03 Boiling Water Reactor Stability Analysis
Mark P. Paulsen, John G. Shatford, John L. Westacott, Lance J. Agee
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 162-173
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34739
Homogenization and Functionalization of One-Dimensional Cross Sections for RETRAN
James T. Cronin, Kord S. Smith
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 174-183
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34740
Transient Analysis of the MSIV-ATWS in a 1000-MW(thermal) BWR-4
Martin A. Zimmermann
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 184-192
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34741
Improved Pressurized Water Reactor Steamline Break Analysis Using RETRAN-02, ARROTTA, and VIPRE-02
Antonio F. Dias, Laurance D. Eisenhart, Diane M. Bell, Terry J. Garrett, Glenn J. Neises, Lance J. Agee
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 193-202
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34742
Analysis of Cofrentes Abnormal Plant Transients with RETRAN-02 and RETRAN-03
Pedro Mata, Pablo García Sedano, Juan Serra
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 203-215
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34743
VIPRE—A Reactor Core Thermal-Hydraulics Analysis Code for Utility Applications
Govinda S. Srikantiah
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 216-227
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34744
Validation of RETRAN-03 by Simulating a Peach Bottom Turbine Trip and Boiloff at the Full Integral Simulation Test Facility
John L. Westacott, Craig E. Peterson, Seung Oh
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 228-245
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34745
VIPRE-02—A Two-Fluid Thermal-Hydraulics Code for Reactor Core and Vessel Analysis: Mathematical Modeling and Solution Methods
Joseph M. Kelly, Charles W. Stewart, Judith M. Cuta
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 246-259
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34746
Applied Research in Critical Heat Flux
Jeffrey T. Dillingham, James H. Stuhmiller
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 260-270
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34747

Number 3

Decay Heat Removal by Natural Circulation in a 550-kW(electric) SP-100 Power System for a Lunar Outpost
Mohamed S. El-Genk, Huimin Xue
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 271-286
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34724
Theoretical and Experimental Analysis of the Bistable Convection Loop for Liquid-Metal-Cooled Reactor Emergency Core Cooling
G. Anand, R. N. Christense
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 287-294
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34725
Knowledge Representation for Automated Boiling Water Reactor Plant Startup
Koichi Sekimizu, Tsuneyasu Araki, Seishiro Kawakami
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 295-309
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34726
Behavior of Mercury in High-Temperature Vitrification Processes
Ronald W. Goles, Langdon K. Holton, Jr., Gary J. Sevigny
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 310-321
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34727
A Radioactivity Assay Method Using Computed Tomography
Tetsuo Goto, Hiroaki Kato
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 322-330
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT92-A34728
Effect of Outside Cooling on the Thermal Behavior of a Pressurized Water Reactor Vessel Lower Head
Hyunjae Park, Vijay K. Dhir
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 331-346
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34729
Two-Phase Flow and Heat Transfer in a Once-Through Steam Generator During Auxiliary Feedwater Injection
B. K. Kamboj, S. M. Ghiaasiaan, and, S. I. Abdel-Khalik
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 347-360
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34730
Application of Optimal Control Theory to a Load-Following Pressurized Water Reactor
Man-Sung Yim, John M. Christenson
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 361-377
Technical Paper | Reactor Operation | doi.org/10.13182/NT92-A34731
On-Line Diagnostic Method with Automated Noise-Signature Learning
Tetsuo Tamaoki, Masuo Sato, Ryoichi Takahashi
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 378-389
Technical Paper | Reactor Operation | doi.org/10.13182/NT92-A34732
Molten Salt Reactors for Burning Dismantled Weapons Fuel
Uri Gat, J. R. Engel, H. L. Dodds
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 390-394
Technical Note | Fission Reactor | doi.org/10.13182/NT92-A34733
Mixed RuO₂/TiO₂/PtO₂-Coated Titanium Anodes for the Electrolytic Dissolution of Nuclear Fuels
U. Kamachi Mudali, R. K. Dayal, J. B. Gnanamoorthy
Nuclear Technology | Volume 100 | Number 3 | December 1992 | Pages 395-402
Technical Note | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34734

Volume 100

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