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Volume 130

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