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Volume 127

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Nuclear Technology / Volume 127 / Number 1

July 1999

Table of Contents

Nuclear Technology / Volume 127 / Number 2

August 1999

Table of Contents

Nuclear Technology / Volume 127 / Number 3

September 1999

Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries

Luiz C. Leal, Otto W. Hermann, Stephen M. Bowman, Cecil V. Parks

Nuclear Technology / Volume 127 / Number 1 / Pages 1-23

July 1999

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Price:$30.00

Drag Coefficients for Reactor Loose Parts

Liang Shi, J. Michael Doster, Charles W. Mayo

Nuclear Technology / Volume 127 / Number 1 / Pages 24-37

July 1999

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Price:$30.00

Modeling the Statics of a Natural-Circulation Boiling Water Reactor Loop

Haico V. Kok, Tim H. J. J. van der Hagen

Nuclear Technology / Volume 127 / Number 1 / Pages 38-48

July 1999

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Qualification of a Three-Dimensional Core Dynamics Analysis Program Coupled with a Detailed Mesh Division for Commercial Boiling Water Reactors-I

Yasunori Bessho, Takafumi Anegawa, Osamu Yokomizo, Yuichiro Yoshimoto, Masao Chaki, Motoo Aoyama, Takanori Fukahori

Nuclear Technology / Volume 127 / Number 1 / Pages 49-65

July 1999

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Natural Convection Heat Transfer with Crust Formation in the Molten Metal Pool

Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Sang-Min Choi

Nuclear Technology / Volume 127 / Number 1 / Pages 66-80

July 1999

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Separation of Radioactive Strontium from Alkaline Nuclear Waste Solutions with the Highly Effective Ion Exchanger SrTreat

Jukka Lehto, Leena Brodkin, Risto Harjula, Esko Tusa

Nuclear Technology / Volume 127 / Number 1 / Pages 81-87

July 1999

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Price:$30.00

Dose Rate Measurements and Calculation of TN-12/2 Packages

Hiroaki Taniuchi, Fumio Matsuda

Nuclear Technology / Volume 127 / Number 1 / Pages 88-101

July 1999

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Price:$30.00

Empirical Steam Generator Water-Level Modeling Using Neural Networks

Chaung Lin, Tsung-Ming Lin

Nuclear Technology / Volume 127 / Number 1 / Pages 102-112

July 1999

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Theoretical Calculations of Proton Reaction Cross Sections in a Lead Target with Energy Ep 300 MeV

Jinfeng Zhou, Qingbiao Shen, Xiuquan Sun

Nuclear Technology / Volume 127 / Number 1 / Pages 113-122

July 1999

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Uncertainty Analysis in DUPIC Fuel-Cycle Cost Using a Probabilistic Simulation Method

Won Il Ko, Jong Won Choi, Jae Sol Lee, Hyun Soo Park, Kun Jai Lee

Nuclear Technology / Volume 127 / Number 1 / Pages 123-140

July 1999

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A MELCOR-Based Model to Calculate Vapor Natural Circulation in Pressurized Water Reactor High-Pressure Severe Accidents

Francisco Martín-Fuertes Hernández-Sonseca

Nuclear Technology / Volume 127 / Number 2 / Pages 141-150

August 1999

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Modeling of the Rim Effect on Thermal Behavior of High-Burnup UO2 Fuel

Byung-Ho Lee, Yang-Hyun Koo, Dong-Seong Sohn

Nuclear Technology / Volume 127 / Number 2 / Pages 151-159

August 1999

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Price:$30.00

Format:

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Core Damage Severity Evaluation for Pressurized Water Reactors by Use of Fuzzy Logic Algorithms

Anastasios Mironidis, Leon Lidofsky, George Grochowski, Lefteris Tsoukalas

Nuclear Technology / Volume 127 / Number 2 / Pages 170-185

August 1999

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Conceivable Limits for Thermal Reactor Spent-Fuel Recycling

David R. Kingdon, Vladimir A. Khotylev, Archie A. Harms, J. Eduard Hoogenboom

Nuclear Technology / Volume 127 / Number 2 / Pages 186-198

August 1999

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Matrix Diffusion of Simple Cations, Anions, and Neutral Species in Fractured Crystalline Rocks

Haruo Sato

Nuclear Technology / Volume 127 / Number 2 / Pages 199-211

August 1999

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Price:$30.00

Evaluation of the Effect of Temperature on Potassium Clinoptilolite Ion Exchange

David A. White, Andreas Nattkemper, Radu Ratautiu

Nuclear Technology / Volume 127 / Number 2 / Pages 212-217

August 1999

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Price:$30.00
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