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ANS > Publications > Journals > Nuclear Technology > Volume 146 |
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Number 1 · Number 2 · Number 3 |
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Number 1 · April 2004 |
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• Table of Contents |
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Simulation of the OECD Main-Steam-Line-Break Benchmark Exercise 3 Using the Coupled RELAP5/PANTHER Codes
Volume 146 · Number 1 · April 2004 · Pages 1-14
Technical Paper · Reactor Safety  Christophe R. Schneidesch, Jinzhao Zhang |
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Consistent Comparison of the Codes RELAP5/PARCS and TRAC-M/PARCS for the OECD MSLB Coupled Code Benchmark
Volume 146 · Number 1 · April 2004 · Pages 15-28
Technical Paper · Thermal Hydraulics Tomasz Kozlowski, R. Matthew Miller, Thomas J. Downar, Douglas A. Barber, Han Gyu Joo |
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Methods and Results for the MSLB NEA Benchmark Using SIMTRAN and RELAP-5
Volume 146 · Number 1 · April 2004 · Pages 29-40
Technical Paper · Thermal Hydraulics José M. Aragonés, Carol Ahnert, Oscar Cabellos, Nuria García-Herranz, Vanessa Aragonés-Ahnert |
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Analysis of a Main-Steam-Line Break in Ascó NPP
Volume 146 · Number 1 · April 2004 · Pages 41-48
Technical Paper · Thermal Hydraulics Arántzazu Cuadra, José-Luis Gago, Francesc Reventós |
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Analytical Study on Fire and Explosion Accidents Assumed in HTGR Hydrogen Production System
Volume 146 · Number 1 · April 2004 · Pages 49-57
Technical Paper · Reactor Safety Yoshitomo Inaba, Tetsuo Nishihara, Yoshikazu Nitta |
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Calculations of the Neutron Flux Outside BWR 8 × 8 Spent-Fuel Assemblies and the Sensitivity to Fuel Pin Diversion
Volume 146 · Number 1 · April 2004 · Pages 58-64
Technical Paper · Fuel Cycle and Management Peter Jansson, Ane Håkansson, Anders Bäcklin |
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A Neural Network Model for the Tomographic Analysis of Irradiated Nuclear Fuel Rods
Volume 146 · Number 1 · April 2004 · Pages 65-71
Technical Paper · Fuel Cycle and Management Teddy Craciunescu |
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Isotopic Transmutations in Irradiated Beryllium and Their Implications on MARIA Reactor Operation
Volume 146 · Number 1 · April 2004 · Pages 72-82
Technical Paper · Radioactive Waste Management and Disposal Krzysztof J. Andrzejewski, Teresa A. Kulikowska |
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Counter-Permeation of Deuterium and Hydrogen Through INCONEL 600®
Volume 146 · Number 1 · April 2004 · Pages 83-95
Technical Paper · Materials for Nuclear Systems Tetsuaki Takeda, Jin Iwatsuki |
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Number 2 · May 2004 |
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• Table of Contents |
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Analysis of Seven NEPTUN-III (Tight-Lattice) Bottom-Flooding Experiments with RELAP5/MOD3.3/BETA
Volume 146 · Number 2 · May 2004 · Pages 99-121
Technical Paper · Thermal Hydraulics G. Th. Analytis |
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A Study of Boron and Temperature Mixing in the Downcomer and the Lower Part of a VVER Reactor Vessel
Volume 146 · Number 2 · May 2004 · Pages 122-130
Technical Paper · Fission Reactors Yury A. Bezrukov, Sergey A. Logvinov, Vladimir N. Ul'yanovsky, Nikolay A. Strebnev |
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Development and Validation of ARKAS_cellule: An Advanced Core-Bowing Analysis Code for Fast Reactors
Volume 146 · Number 2 · May 2004 · Pages 131-142
Technical Paper · Fission Reactors Hirokazu Ohta, Takeshi Yokoo, Masatoshi Nakagawa, Shinichiro Matsuyama |
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Criticality Data for Spherical 235U, 239Pu, and 237Np Systems Reflector-Moderated by Low Capturing-Moderator Materials
Volume 146 · Number 2 · May 2004 · Pages 143-154
Technical Paper · Reactor Safety David J. Loaiza, William Stratton |
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Advanced MOX Core Design Study of Sodium-Cooled Reactors in Current Feasibility Study on Commercialized Fast Reactor Cycle Systems in Japan
Volume 146 · Number 2 · May 2004 · Pages 155-163
Technical Paper · Fuel Cycle and Management Tomoyasu Mizuno, Hajime Niwa |
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Mechanical Analysis of High Power Internally Cooled Annular Fuel
Volume 146 · Number 2 · May 2004 · Pages 164-180
Technical Paper · Thermal Hydraulics Jiyun Zhao, Hee Cheon No, Mujid S. Kazimi |
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Decision Analysis and Its Application to the Frequency of Containment Integrated Leakage Rate Tests
Volume 146 · Number 2 · May 2004 · Pages 181-198
Technical Paper · Nuclear Plant Operations and Control George E. Apostolakis, John P. Koser, Gaku Sato |
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Analysis of PWR RCS Injection Strategy During Severe Accident
Volume 146 · Number 2 · May 2004 · Pages 199-205
Technical Note · Reactor Safety Shih-Jen Wang, Kwang-Sheng Chiang, Show-Chyuan Chiang |
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A Simple Kinetic Model for the Alpha Radiolysis of Water Sorbed on NpO2
Volume 146 · Number 2 · May 2004 · Pages 206-209
Technical Note · Nuclear Plant Operations and Control Alan S. Icenhour, Louis M. Toth, Robert M. Wham, R. R. Brunson |
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Number 3 · June 2004 |
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• Table of Contents |
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Effect of Replacing Helium with a Liquid Metal in the Fuel-Cladding Gap on Fission Gas Release
Volume 146 · Number 3 · June 2004 · Pages 211-220
Technical Paper · Fuel Cycle and Management Doonyapong Wongsawaeng, Donald R. Olander |
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A Simplified Approach for Evaluation of the Burnup Potential of Alternative Fuels
Volume 146 · Number 3 · June 2004 · Pages 221-229
Technical Paper · Fuel Cycle and Management Stella Maris Oggianu, Hee Cheon No, Mujid S. Kazimi |
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WISE: A New Fuel Cycle Concept Based on a Mobile Fuel Reactor
Volume 146 · Number 3 · June 2004 · Pages 230-243
Technical Paper · Fuel Cycle and Management Igor Slessarev, G. Palmiotti, M. Salvatores, V. Berthou |
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Investigating the Nonlinear Dynamics of Natural-Circulation, Boiling Two-Phase Flows
Volume 146 · Number 3 · June 2004 · Pages 244-256
Technical Paper · Thermal Hydraulics Robert Zboray, Wilhelmus J. M. de Kruijf, Tim H. J. J. van der Hagen, Rizwan-uddin |
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IIST Passive Core Cooling on Pressurizer Top Break
Volume 146 · Number 3 · June 2004 · Pages 257-266
Technical Paper · Thermal Hydraulics Tay-Jian Liu, Chien-Hsiung Lee |
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Multilevel Methodology in Parallel Computing Environment for Evaluating BWR Safety Parameters
Volume 146 · Number 3 · June 2004 · Pages 267-278
Technical Paper · Thermal Hydraulics Jorge Solís, Maria N. Avramova, Kostadin N. Ivanov |
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Experimental Validation of CFD Analyses for Estimating the Transport Fraction of LOCA-Generated Insulation Debris to ECCS Sump Screens
Volume 146 · Number 3 · June 2004 · Pages 279-289
Technical Paper · Thermal Hydraulics Arup K. Maji, Bruce Letellier, Kyle W. Ross, Daseri V. Rao, Luke Bartlein |
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A Fuzzy Modeling Approach to Road Transport with Application to a Case of Spent Nuclear Fuel Transport
Volume 146 · Number 3 · June 2004 · Pages 290-302
Technical Paper · Criticality of Nuclear Materials Marzio Marseguerra, Enrico Zio, Mauro Bianchi |
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Radiation Shielding Analysis for Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors (DUPIC)
Volume 146 · Number 3 · June 2004 · Pages 303-324
Technical Paper · Radiation Protection Gyuhong Roh, Hangbok Choi |
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The Use of Molybdenum-Based Ceramic-Metal (CerMet) Fuel for the Actinide Management in LWRs
Volume 146 · Number 3 · June 2004 · Pages 325-331
Technical Paper · Radioactive Waste Management and Disposal Klaas Bakker, Frodo C. Klaassen, Ronald P. C. Schram, Alfred Hogenbirk, Robin Klein Meulekamp, Arjan Bos, Hubert Rakhorst, Charles A. Mol |
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