ANS / Publications / Journals / Nuclear Technology

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT04-A3464

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT04-A3472

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT04-A3481