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Number 1

Table of Contents

Monte Carlo Modeling of the Texas A&M University Research Reactor
Chan-Hyeong Kim, Siyoung Jang, Warren Dan Reece
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 1-10
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3455
A Simple and Efficient Control Rod Cusping Model for Three-Dimensional Pin-by-Pin Core Calculations
Akio Yamamoto
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 11-17
Technical Paper | Fission Reactors | doi.org/10.13182/NT145-11
Steam Line Break and Station Blackout Transients for Proliferation-Resistant Hexagonal Tight Lattice Boiling Water Reactor
Upendra S. Rohatgi, Jae H. Jo, Bub Dong Chung, Hiroshi Takahashi, Thomas J. Downar
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 18-27
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3457
Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Reactors and Safety Code Validation
László Szabados
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 28-43
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3458
Feasibility of Increasing the Advanced Test Reactor's Maximum Lobe Power by Adding an Accumulator Injection System
Steven T. Polkinghorne, Gregg L. Sharp, Richard T. McCracken
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 44-56
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3459
Thermal Behavior of the Reactor Vessel Penetration Under External Vessel Cooling During a Severe Accident
Kyoung-Ho Kang, Rae-Joon Park, Jong-Tae Kim, Byung-Tae Min, Ki-Young Lee, Sang-Baik Kim
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 57-66
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3460
Uranium Transport in a High-Throughput Electrorefiner for EBR-II Blanket Fuel
Rajesh K. Ahluwalia, Thanh Q. Hua, DeeEarl Vaden
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 67-81
Technical Paper | Reprocessing | doi.org/10.13182/NT04-A3461
Application of Polymers for the Long-Term Storage and Disposal of Low- and Intermediate-Level Radioactive Waste
Hugues W. Bonin, Michael W. Walker, Van Tam Bui
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 82-101
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT04-A3462
Experimental and Analytical Studies on the Penetration Integrity of the Reactor Vessel Under External Vessel Cooling
Rae-Joon Park, Kyoung-Ho Kang, Jong-Tae Kim, Ki-Young Lee, Sang-Baik Kim
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 102-114
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT04-A3463
Transient Fuel Behavior and Failure Condition in the CABRI-2 Experiments
Ikken Sato, Francette Lemoine, Dankward Struwe
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 115-137
Technical Paper | Environmental Science, Technology, and Effects | doi.org/10.13182/NT04-A3464

Number 2

Table of Contents

Determination of Limit Cycles Using Both the Slope of Correlation Integral and Dominant Lyapunov Methods
Rogelio Castillo, Gustavo Alonso, Javier C. Palacios
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 139-149
Technical Paper | Reactor Safety | doi.org/10.13182/NT04-A3465
Dynamic Comparison of Three- and Four-Equation Reactor Core Models in a Full-Scope Power Plant Training Simulator
Gilberto Espinosa-Paredes, Jose Alvarez-Ramirez, Alejandro Nuñez-Carrera, Alfonso Garcia-Gutierrez, Elizabeth Jeannette Martinez-Mendez
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 150-162
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3466
Void Fraction and Critical Power Assessment of CORETRAN-01/VIPRE-02
Yacine Aounallah
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 163-176
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3467
Application of Wavelet Noise-Reduction Technique to Water-Level Controller
Gee Yong Park, Jinho Park, Poong Hyun Seong
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 177-188
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3468
A Personal Computer-Based Simulation-and-Control-Integrated Platform for 10-MW High-Temperature Gas-Cooled Reactor
Lei Shi, Haibin Liu, Xiaojing Yang, Zuying Gao, Yujie Dong, Zuoyi Zhang
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 189-203
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3469
Evaluation of ²³⁵U Isotopic Dilution with the Addition of Depleted Uranium to Supernatant Liquid Waste
Lawrence N. Oji, David T. Hobbs, Paul D. d'Entremont
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 204-214
Technical Paper | Reprocessing | doi.org/10.13182/NT04-A3470
Evaluation of Uranium Coprecipitation with Sodium Aluminosilicate Phases
Lawrence N. Oji, Adrienne L. Williams
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 215-229
Technical Paper | Reprocessing | doi.org/10.13182/NT04-A3471
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
Tomoyuki Uwaba, Masahiro Ito, Shigeharu Ukai
Nuclear Technology | Volume 145 | Number 2 | February 2004 | Pages 230-237
Technical Note | Materials for Nuclear Systems | doi.org/10.13182/NT04-A3472

Number 3

Table of Contents

Design of Recycle Pressurized Water Reactor with Heavy Water Moderation
Koki Hibi, Masato Uchita
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 239-246
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3473
ABWR-II Core Design with Spectral Shift Rods for Operation with All Control Rods Withdrawn
Masanao Moriwaki, Motoo Aoyama, Takafumi Anegawa, Hiroyuki Okada, Koichi Sakurada, Akira Tanabe
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 247-256
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3474
Technology Development Issues for High-Conversion BWRs Using Island-Type MOX Fuel
Takao Kondo, Takaaki Mochida, Junichi Yamashita
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 257-265
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3475
Utilization/Disposition of Reactor-Grade Plutonium in High-Temperature Gas-Cooled Reactors
Bernard Bonin, Dominique Grenéche, Frank Carré, Frédéric Damian, Jean-Yves Doriath
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 266-274
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT04-A3476
Prognostics and Condition-Based Maintenance: A New Approach to Precursive Metrics
Donald B. Jarrell, Daniel R. Sisk, Leonard J. Bond
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 275-286
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3477
System Analysis for Decay Heat Removal in Lead-Bismuth-Cooled Natural-Circulation Reactors
Takaaki Sakai, Yasuhiro Enuma, Takashi Iwasaki
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 287-297
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3478
An Experimental Study of Sweepout and Entrainment in the Advanced Reactor Downcomer
Sang H. Yoon, Kune Y. Suh
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 298-310
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT04-A3479
Gas Core Reactor with Magnetohydrodynamic Power System and Cascading Power Cycle
Blair M. Smith, Samim Anghaie
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 311-318
Technical Note | Fission Reactors | doi.org/10.13182/NT04-A3480
A Proposed Method for the Determination of Leakage Rate for a Reactor Containment Vessel
Mark A. Tries, Leo M. Bobek
Nuclear Technology | Volume 145 | Number 3 | March 2004 | Pages 319-323
Technical Note | Nuclear Plant Operations and Control | doi.org/10.13182/NT04-A3481

Volume 145

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