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Volume 130

Number 1 | Number 2 | Number 3

Number 1

A Pin Power Reconstruction Method for CANDU Reactor Cores Based on Coarse-Mesh Finite Difference Calculations

Hyung-Seok Lee, Won Sik Yang, Man Gyun Na, Hangbok Choi

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 1-8

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3072

Fission Gas Release from UO2+x in Defective Fuel Rods

Yeon Soo Kim

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 9-17

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3073

RELAP5 Simulation of Thermal-Hydraulic Behavior in a CANDU Reactor - Assessments of RD-14 Experiments

Sukho Lee, In-Goo Kim

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 18-26

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3074

Development of a Dynamic Event Tree for a Pressurized Water Reactor Steam Generator Tube Rupture Event

Chun-Chang Chao, Chin-Jang Chang

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 27-38

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3075

Heat Transfer Modeling During a Vapor Explosion

Georges Berthoud

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 39-58

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3076

Hydrogen Water Chemistry Technology in Boiling Water Reactors

Chien C. Lin

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 59-70

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT00-A3077

Analysis of Radionuclide Release from Spent Ion-Exchange Resins

Sol-Il Su, Man-Sung Yim

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 71-88

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3078

Alternatives to High-Level Waste Vitrification: The Need for Common Sense

Jimmy T. Bell

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 89-98

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3079

A Comparison of Natural Convection Heat Transfer for a Staggered Versus an Aligned Array of Horizontal Spent Nuclear Fuel Rods Within a Rectangular Enclosure

C. Eric Triplett, Robert E. Canaan, Dale E. Klein

Nuclear Technology / Volume 130 / Number 1 / April 2000 / Pages 99-110

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3080

Number 2

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

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

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 111-131

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3081

A Formal Procedure for Probabilistic Quantification of Modeling Uncertainties Employed in Phenomenological Transient Models

Kwang-Il Ahn, Hee-Dong Kim

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 132-144

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3082

Experimental Breeder Reactor-II Frequency Response Test Measurements Via Pseudorandom, Discrete-Level Binary and Ternary Signals

William D. Rhodes, Raymond V. Furstenau, Howard A. Larson

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 145-158

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3083

Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels

Jean-M. Paratte, Hiroshi Akie, Rakesh Chawla, Marc Delpech, Jan Leen Kloosterman, Carlo Lombardi, Alessandro Mazzola, Sandro Pelloni, Yannick Pénéliau, Hideki Takano

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 159-176

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3084

Comparative Study of Station Blackout Counterpart Tests in APEX and ROSA/AP600

Abd Y. Lafi, Jose N. Reyes, Jr.

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 177-183

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3085

Metal Surface Decontamination Using 1-Hydroxyethane-1,1-Diphosphonic Acid

Michael D. Kaminski, Luis Nuñez, Ankur Purohit, Michael Lewandowski

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 184-195

Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT00-A3086

Radioactive Waste Minimization by Electrolytic Extraction and Destruction in a Purex-Truex Actinide Separation System

Masaki Ozawa, Yuichi Sano, Chisako Ohara, Takamichi Kishi

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 196-205

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3087

Measurements of the Effective Diffusion Coefficient of Dissolved Oxygen and Oxidation Rate of Pyrite by Dissolved Oxygen in Compacted Sodium Bentonite

Mitsuo Manaka, Manabu Kawasaki, Akira Honda

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 206-217

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3088

Fracture Mechanism of Borated Stainless Steel

J. Y. He, Salah E. Soliman, Anthony J. Baratta, Thomas A. Balliett

Nuclear Technology / Volume 130 / Number 2 / May 2000 / Pages 218-225

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT00-A3089

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

 

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