ANS / Publications / Journals / Nuclear Technology

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT92-A34759

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT92-A34747

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT92-A34734