American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 145

Volume 145

Number 1 | Number 2 | Number 3

Number 1

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

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

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

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

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

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

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

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

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

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

Number 2

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

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

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

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

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

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

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

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

Number 3

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

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

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

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

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

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

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

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

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

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement