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Volume 130

Number 3

Plutonium Recycling in Pressurized Water Reactors: Influence of the Moderator-to-Fuel Ratio

Jan Leen Kloosterman, Evert E. Bende

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 227-241

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3090

A Recriticality-Free Fast Reactor Core Concept

Tetsuo Sawada, Hisashi Ninokata, Hirofumi Tomozoe, Hiroshi Endo

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 242-251

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT130-242

Fuel Pin Behavior Under the Slow Power Ramp Transients in the CABRI-2 Experiments

Jean Charpenel, Francette Lemoine, Ikken Sato, Dankward Struwe, Werner Pfrang

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 252-271

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3092

Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

Kazuo Minato, Toru Ogawa, Kazuhiro Sawa, Akiyoshi Ishikawa, Takeshi Tomita, Shozo Iida, Hajime Sekino

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 272-281

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3093

In-Core Fuel Management with Biased Multiobjective Function Optimization

Youssef A. Shatilla, David C. Little, Jack A. Penkrot, Richard Andrew Holland

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 282-295

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3094

Analysis of Transient Events Without Scram in a Research Reactor Using the RELAP5/MOD3.2 Computer Code

Sridhar Hari, Yassin A. Hassan, Jiyuan Tu

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 296-309

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3095

A Procedure to Predict Subcooled-Water-Flow-Boiling CHF in Uniformly Heated Tubes for High-Heat-Flux Applications

Young Min Kwon, Soon Heung Chang

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 310-328

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3096

Risk-Informed Assessment of the Technical Specifications of PWR RPS Instrumentation

Ioannis A. Papazoglou

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 329-350

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT00-A3097

An Approximate Reasoning-Based Method for Screening High-Level-Waste Tanks for Flammable Gas

Stephen W. Eisenhawer, Terry F. Bott, Ronald E. Smith

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 351-361

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3098

Interaction Between Molecular Iodine in a Gas Phase and Paints Aged in a Nuclear Power Plant

André Zoulalian, Edith Belval-Haltier

Nuclear Technology / Volume 130 / Number 3 / June 2000 / Pages 362-371

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT00-A3099