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ANS > Publications > Journals > Nuclear Technology > Volume 130 |
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Number 1 · Number 2 · Number 3 |
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Number 1 · April 2000 |
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• Table of Contents |
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A Pin Power Reconstruction Method for CANDU Reactor Cores Based on Coarse-Mesh Finite Difference Calculations
Volume 130 · Number 1 · April 2000 · Pages 1-8
Technical Paper · Fission Reactors  Hyung-Seok Lee, Won Sik Yang, Man Gyun Na, Hangbok Choi |
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Fission Gas Release from UO2+x in Defective Fuel Rods
Volume 130 · Number 1 · April 2000 · Pages 9-17
Technical Paper · Fuel Cycle and Management Yeon Soo Kim |
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RELAP5 Simulation of Thermal-Hydraulic Behavior in a CANDU Reactor - Assessments of RD-14 Experiments
Volume 130 · Number 1 · April 2000 · Pages 18-26
Technical Paper · Thermal Hydraulics Sukho Lee, In-Goo Kim |
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Development of a Dynamic Event Tree for a Pressurized Water Reactor Steam Generator Tube Rupture Event
Volume 130 · Number 1 · April 2000 · Pages 27-38
Technical Paper · Thermal Hydraulics Chun-Chang Chao, Chin-Jang Chang |
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Heat Transfer Modeling During a Vapor Explosion
Volume 130 · Number 1 · April 2000 · Pages 39-58
Technical Paper · Thermal Hydraulics Georges Berthoud |
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Hydrogen Water Chemistry Technology in Boiling Water Reactors
Volume 130 · Number 1 · April 2000 · Pages 59-70
Technical Paper · Nuclear Plant Operations and Control Chien C. Lin |
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Analysis of Radionuclide Release from Spent Ion-Exchange Resins
Volume 130 · Number 1 · April 2000 · Pages 71-88
Technical Paper · Radioactive Waste Management and Disposal Sol-Il Su, Man-Sung Yim |
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Alternatives to High-Level Waste Vitrification: The Need for Common Sense
Volume 130 · Number 1 · April 2000 · Pages 89-98
Technical Paper · Radioactive Waste Management and Disposal Jimmy T. Bell |
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A Comparison of Natural Convection Heat Transfer for a Staggered Versus an Aligned Array of Horizontal Spent Nuclear Fuel Rods Within a Rectangular Enclosure
Volume 130 · Number 1 · April 2000 · Pages 99-110
Technical Note · Thermal Hydraulics C. Eric Triplett, Robert E. Canaan, Dale E. Klein |
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Number 2 · May 2000 |
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• Table of Contents |
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Criticality and Safety Parameter Studies of a 3-MW TRIGA MARK-II Research Reactor and Validation of the Generated Cross-Section Library and Computational Method
Volume 130 · Number 2 · May 2000 · Pages 111-131
Technical Paper · Fission Reactors S. I. Bhuiyan, M. A. W. Mondal, M. M. Sarker, M. Rahman, M. S. Shahdatullah, M. Q. Huda, T. K. Chakrobortty, M. J. H. Khan |
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A Formal Procedure for Probabilistic Quantification of Modeling Uncertainties Employed in Phenomenological Transient Models
Volume 130 · Number 2 · May 2000 · Pages 132-144
Technical Paper · Reactor Safety Kwang-Il Ahn, Hee-Dong Kim |
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Experimental Breeder Reactor-II Frequency Response Test Measurements Via Pseudorandom, Discrete-Level Binary and Ternary Signals
Volume 130 · Number 2 · May 2000 · Pages 145-158
Technical Paper · Reactor Safety William D. Rhodes, Raymond V. Furstenau, Howard A. Larson |
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Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels
Volume 130 · Number 2 · May 2000 · Pages 159-176
Technical Paper · Fuel Cycle and Management Jean-M. Paratte, Hiroshi Akie, Rakesh Chawla, Marc Delpech, Jan Leen Kloosterman, Carlo Lombardi, Alessandro Mazzola, Sandro Pelloni, Yannick Pénéliau, Hideki Takano |
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Comparative Study of Station Blackout Counterpart Tests in APEX and ROSA/AP600
Volume 130 · Number 2 · May 2000 · Pages 177-183
Technical Paper · Thermal Hydraulics Abd Y. Lafi, Jose N. Reyes, Jr. |
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Metal Surface Decontamination Using 1-Hydroxyethane-1,1-Diphosphonic Acid
Volume 130 · Number 2 · May 2000 · Pages 184-195
Technical Paper · Decontamination/Decommissioning Michael D. Kaminski, Luis Nuñez, Ankur Purohit, Michael Lewandowski |
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Radioactive Waste Minimization by Electrolytic Extraction and Destruction in a Purex-Truex Actinide Separation System
Volume 130 · Number 2 · May 2000 · Pages 196-205
Technical Paper · Radioactive Waste Management and Disposal Masaki Ozawa, Yuichi Sano, Chisako Ohara, Takamichi Kishi |
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Measurements of the Effective Diffusion Coefficient of Dissolved Oxygen and Oxidation Rate of Pyrite by Dissolved Oxygen in Compacted Sodium Bentonite
Volume 130 · Number 2 · May 2000 · Pages 206-217
Technical Paper · Radioactive Waste Management and Disposal Mitsuo Manaka, Manabu Kawasaki, Akira Honda |
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Fracture Mechanism of Borated Stainless Steel
Volume 130 · Number 2 · May 2000 · Pages 218-225
Technical Paper · Materials for Nuclear Systems J. Y. He, Salah E. Soliman, Anthony J. Baratta, Thomas A. Balliett |
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Number 3 · June 2000 |
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• Table of Contents |
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Plutonium Recycling in Pressurized Water Reactors: Influence of the Moderator-to-Fuel Ratio
Volume 130 · Number 3 · June 2000 · Pages 227-241
Technical Paper · Fission Reactors Jan Leen Kloosterman, Evert E. Bende |
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A Recriticality-Free Fast Reactor Core Concept
Volume 130 · Number 3 · June 2000 · Pages 242-251
Technical Paper · Fission Reactors Tetsuo Sawada, Hisashi Ninokata, Hirofumi Tomozoe, Hiroshi Endo |
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Fuel Pin Behavior Under the Slow Power Ramp Transients in the CABRI-2 Experiments
Volume 130 · Number 3 · June 2000 · Pages 252-271
Technical Paper · Reactor Safety Jean Charpenel, Francette Lemoine, Ikken Sato, Dankward Struwe, Werner Pfrang |
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Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors
Volume 130 · Number 3 · June 2000 · Pages 272-281
Technical Paper · Fuel Cycle and Management Kazuo Minato, Toru Ogawa, Kazuhiro Sawa, Akiyoshi Ishikawa, Takeshi Tomita, Shozo Iida, Hajime Sekino |
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In-Core Fuel Management with Biased Multiobjective Function Optimization
Volume 130 · Number 3 · June 2000 · Pages 282-295
Technical Paper · Fuel Cycle and Management Youssef A. Shatilla, David C. Little, Jack A. Penkrot, Richard Andrew Holland |
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Analysis of Transient Events Without Scram in a Research Reactor Using the RELAP5/MOD3.2 Computer Code
Volume 130 · Number 3 · June 2000 · Pages 296-309
Technical Paper · Thermal Hydraulics Sridhar Hari, Yassin A. Hassan, Jiyuan Tu |
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A Procedure to Predict Subcooled-Water-Flow-Boiling CHF in Uniformly Heated Tubes for High-Heat-Flux Applications
Volume 130 · Number 3 · June 2000 · Pages 310-328
Technical Paper · Thermal Hydraulics Young Min Kwon, Soon Heung Chang |
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Risk-Informed Assessment of the Technical Specifications of PWR RPS Instrumentation
Volume 130 · Number 3 · June 2000 · Pages 329-350
Technical Paper · Nuclear Plant Operations and Control Ioannis A. Papazoglou |
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An Approximate Reasoning-Based Method for Screening High-Level-Waste Tanks for Flammable Gas
Volume 130 · Number 3 · June 2000 · Pages 351-361
Technical Paper · Radioactive Waste Management and Disposal Stephen W. Eisenhawer, Terry F. Bott, Ronald E. Smith |
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Interaction Between Molecular Iodine in a Gas Phase and Paints Aged in a Nuclear Power Plant
Volume 130 · Number 3 · June 2000 · Pages 362-371
Technical Paper · Radioisotopes André Zoulalian, Edith Belval-Haltier |
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