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ANS > Publications > Journals > Nuclear Technology > Volume 145
Number 1  ·  Number 2  ·  Number 3
Number 1 · January 2004
Table of Contents
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
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
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
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
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
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
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
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
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
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
Number 2 · February 2004
Table of Contents
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
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
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
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
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
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
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
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
Number 3 · March 2004
Table of Contents
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
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
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
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
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
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
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
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
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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