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Number 1 · January 2004
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Table of Contents
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Monte Carlo Modeling of the Texas A&M University Research Reactor
Volume 145 · Number 1 · January 2004 · Pages 1-10
Technical Paper · Fission Reactors

Chan-Hyeong Kim, Siyoung Jang, Warren Dan Reece
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A Simple and Efficient Control Rod Cusping Model for Three-Dimensional Pin-by-Pin Core Calculations
Volume 145 · Number 1 · January 2004 · Pages 11-17
Technical Paper · Fission Reactors

Akio Yamamoto
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Steam Line Break and Station Blackout Transients for Proliferation-Resistant Hexagonal Tight Lattice Boiling Water Reactor
Volume 145 · Number 1 · January 2004 · Pages 18-27
Technical Paper · Fission Reactors

Upendra S. Rohatgi, Jae H. Jo, Bub Dong Chung, Hiroshi Takahashi, Thomas J. Downar
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Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Reactors and Safety Code Validation
Volume 145 · Number 1 · January 2004 · Pages 28-43
Technical Paper · Thermal Hydraulics

László Szabados
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Feasibility of Increasing the Advanced Test Reactor's Maximum Lobe Power by Adding an Accumulator Injection System
Volume 145 · Number 1 · January 2004 · Pages 44-56
Technical Paper · Thermal Hydraulics

Steven T. Polkinghorne, Gregg L. Sharp, Richard T. McCracken
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Thermal Behavior of the Reactor Vessel Penetration Under External Vessel Cooling During a Severe Accident
Volume 145 · Number 1 · January 2004 · Pages 57-66
Technical Paper · Thermal Hydraulics

Kyoung-Ho Kang, Rae-Joon Park, Jong-Tae Kim, Byung-Tae Min, Ki-Young Lee, Sang-Baik Kim
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Uranium Transport in a High-Throughput Electrorefiner for EBR-II Blanket Fuel
Volume 145 · Number 1 · January 2004 · Pages 67-81
Technical Paper · Reprocessing

Rajesh K. Ahluwalia, Thanh Q. Hua, DeeEarl Vaden
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Application of Polymers for the Long-Term Storage and Disposal of Low- and Intermediate-Level Radioactive Waste
Volume 145 · Number 1 · January 2004 · Pages 82-101
Technical Paper · Radioactive Waste Management and Disposal

Hugues W. Bonin, Michael W. Walker, Van Tam Bui
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Experimental and Analytical Studies on the Penetration Integrity of the Reactor Vessel Under External Vessel Cooling
Volume 145 · Number 1 · January 2004 · Pages 102-114
Technical Paper · Materials for Nuclear Systems

Rae-Joon Park, Kyoung-Ho Kang, Jong-Tae Kim, Ki-Young Lee, Sang-Baik Kim
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Transient Fuel Behavior and Failure Condition in the CABRI-2 Experiments
Volume 145 · Number 1 · January 2004 · Pages 115-137
Technical Paper · Environmental Science, Technology, and Effects

Ikken Sato, Francette Lemoine, Dankward Struwe
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Number 2 · February 2004
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Table of Contents
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Determination of Limit Cycles Using Both the Slope of Correlation Integral and Dominant Lyapunov Methods
Volume 145 · Number 2 · February 2004 · Pages 139-149
Technical Paper · Reactor Safety

Rogelio Castillo, Gustavo Alonso, Javier C. Palacios
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Dynamic Comparison of Three- and Four-Equation Reactor Core Models in a Full-Scope Power Plant Training Simulator
Volume 145 · Number 2 · February 2004 · Pages 150-162
Technical Paper · Thermal Hydraulics

Gilberto Espinosa-Paredes, Jose Alvarez-Ramirez, Alejandro Nuñez-Carrera, Alfonso Garcia-Gutierrez, Elizabeth Jeannette Martinez-Mendez
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Void Fraction and Critical Power Assessment of CORETRAN-01/VIPRE-02
Volume 145 · Number 2 · February 2004 · Pages 163-176
Technical Paper · Thermal Hydraulics

Yacine Aounallah
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Application of Wavelet Noise-Reduction Technique to Water-Level Controller
Volume 145 · Number 2 · February 2004 · Pages 177-188
Technical Paper · Thermal Hydraulics

Gee Yong Park, Jinho Park, Poong Hyun Seong
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A Personal Computer-Based Simulation-and-Control-Integrated Platform for 10-MW High-Temperature Gas-Cooled Reactor
Volume 145 · Number 2 · February 2004 · Pages 189-203
Technical Paper · Nuclear Plant Operations and Control

Lei Shi, Haibin Liu, Xiaojing Yang, Zuying Gao, Yujie Dong, Zuoyi Zhang
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Evaluation of 235U Isotopic Dilution with the Addition of Depleted Uranium to Supernatant Liquid Waste
Volume 145 · Number 2 · February 2004 · Pages 204-214
Technical Paper · Reprocessing

Lawrence N. Oji, David T. Hobbs, Paul D. d'Entremont
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Evaluation of Uranium Coprecipitation with Sodium Aluminosilicate Phases
Volume 145 · Number 2 · February 2004 · Pages 215-229
Technical Paper · Reprocessing

Lawrence N. Oji, Adrienne L. Williams
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Development of a Fast Breeder Reactor Fuel Bundle Deformation Analysis Code - BAMBOO: Development of a Pin Dispersion Model and Verification by the Out-of-Pile Compression Test
Volume 145 · Number 2 · February 2004 · Pages 230-237
Technical Note · Materials for Nuclear Systems

Tomoyuki Uwaba, Masahiro Ito, Shigeharu Ukai
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Number 3 · March 2004
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Table of Contents
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Design of Recycle Pressurized Water Reactor with Heavy Water Moderation
Volume 145 · Number 3 · March 2004 · Pages 239-246
Technical Paper · Fission Reactors

Koki Hibi, Masato Uchita
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ABWR-II Core Design with Spectral Shift Rods for Operation with All Control Rods Withdrawn
Volume 145 · Number 3 · March 2004 · Pages 247-256
Technical Paper · Fission Reactors

Masanao Moriwaki, Motoo Aoyama, Takafumi Anegawa, Hiroyuki Okada, Koichi Sakurada, Akira Tanabe
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Technology Development Issues for High-Conversion BWRs Using Island-Type MOX Fuel
Volume 145 · Number 3 · March 2004 · Pages 257-265
Technical Paper · Fission Reactors

Takao Kondo, Takaaki Mochida, Junichi Yamashita
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Utilization/Disposition of Reactor-Grade Plutonium in High-Temperature Gas-Cooled Reactors
Volume 145 · Number 3 · March 2004 · Pages 266-274
Technical Paper · Fuel Cycle and Management

Bernard Bonin, Dominique Grenéche, Frank Carré, Frédéric Damian, Jean-Yves Doriath
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Prognostics and Condition-Based Maintenance: A New Approach to Precursive Metrics
Volume 145 · Number 3 · March 2004 · Pages 275-286
Technical Paper · Nuclear Plant Operations and Control

Donald B. Jarrell, Daniel R. Sisk, Leonard J. Bond
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System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors
Volume 145 · Number 3 · March 2004 · Pages 287-297
Technical Paper · Thermal Hydraulics

Takaaki Sakai, Yasuhiro Enuma, Takashi Iwasaki
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An Experimental Study of Sweepout and Entrainment in the Advanced Reactor Downcomer
Volume 145 · Number 3 · March 2004 · Pages 298-310
Technical Paper · Thermal Hydraulics

Sang H. Yoon, Kune Y. Suh
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Gas Core Reactor with Magnetohydrodynamic Power System and Cascading Power Cycle
Volume 145 · Number 3 · March 2004 · Pages 311-318
Technical Note · Fission Reactors

Blair M. Smith, Samim Anghaie
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A Proposed Method for the Determination of Leakage Rate for a Reactor Containment Vessel
Volume 145 · Number 3 · March 2004 · Pages 319-323
Technical Note · Nuclear Plant Operations and Control

Mark A. Tries, Leo M. Bobek
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