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Volume 130

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Nuclear Technology / Volume 130 / Number 1

April 2000

Table of Contents

Nuclear Technology / Volume 130 / Number 2

May 2000

Table of Contents

Nuclear Technology / Volume 130 / Number 3

June 2000

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 / Pages 1-8

April 2000

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Fission Gas Release from UO2+x in Defective Fuel Rods

Yeon Soo Kim

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

April 2000

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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 / Pages 18-26

April 2000

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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 / Pages 27-38

April 2000

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Heat Transfer Modeling During a Vapor Explosion

Georges Berthoud

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

April 2000

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Hydrogen Water Chemistry Technology in Boiling Water Reactors

Chien C. Lin

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

April 2000

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Analysis of Radionuclide Release from Spent Ion-Exchange Resins

Sol-Il Su, Man-Sung Yim

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

April 2000

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

Jimmy T. Bell

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

April 2000

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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

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

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

April 2000

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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

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 / Pages 111-131

May 2000

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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 / Pages 132-144

May 2000

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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 / Pages 145-158

May 2000

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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 / Pages 159-176

May 2000

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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 / Pages 177-183

May 2000

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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 / Pages 184-195

May 2000

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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 / Pages 196-205

May 2000

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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

Mitsuo Manaka, Manabu Kawasaki, Akira Honda

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

May 2000

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