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Volume 112

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A Utility Perspective on Subchannel Analysis

Gregg B. Swindlehurst

Nuclear Technology / Volume 112 / Number 3 / Pages 355-358

December 1995

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Equilibrium Quality and Mass Flux Distributions in an Adiabatic Three-Subchannel Test Section

George Yadigaroglu, Athan Maganas

Nuclear Technology / Volume 112 / Number 3 / Pages 359-372

December 1995

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Reactor Subchannel Analysis—Electric Power Research Institute Perspective

G. Srikantiah

Nuclear Technology / Volume 112 / Number 3 / Pages 373-381

December 1995

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The Japanese Utilities’ Expectations for Subchannel Analysis

Akio Toba, Akira Omoto

Nuclear Technology / Volume 112 / Number 3 / Pages 382-387

December 1995

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Void Fraction Distribution in A Boiling Water Reactor Fuel Assembly and the Evaluation of Subchannel Analysis Codes

Akira Inoue, Masanobu Futakuchi, Makoto Yagi, Toru Mitsutake, Shin-Ichi Morooka

Nuclear Technology / Volume 112 / Number 3 / Pages 388-400

December 1995

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Subchannel Thermal-Hydraulic Analysis at AP600 Low-Flow Steam-Line-Break Conditions

T. Morita, C. A. Olson, Y. X. Sung, J. F. Connelley, Jr., E. H. Novendstern, S. Kapil, P. W. Rosenthal

Nuclear Technology / Volume 112 / Number 3 / Pages 401-411

December 1995

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Pressurized Water Reactor Fuel Assembly Subchannel Void Fraction Measurement

Yoshiei Akiyama, Keiichi Hori, Keiji Miyazaki, Kaichiro Mishima, Shigekazu Sugiyama

Nuclear Technology / Volume 112 / Number 3 / Pages 412-421

December 1995

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Technical Reviewers

Nuclear Technology / Volume 112 / Number 3 / Pages 422-424

December 1995

Table of Contents

Nuclear Technology / Volume 112 / Number 2

November 1995

Mitigation of an Anticipated Transient Without Scram Event in A Simplified Boiling Water Reactor by the Insertion of Fine-Motion Control Rods

Hasna J. Khan, Hsiang S. Cheng, Upendra S. Rohatgi

Nuclear Technology / Volume 112 / Number 2 / Pages 155-168

November 1995

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Independent Assessment of Melcor as A Severe Accident Thermal-Hydraulic/Source Term Analysis Tool

I. K. Madni

Nuclear Technology / Volume 112 / Number 2 / Pages 169-180

November 1995

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A Comparative Simulation of Feed and Bleed Operation During the Total Loss of Feedwater Event by RELAP5/MOD3 and CEFLASH-4AS/REM Computer Codes

Young Min Kwon, Tae Sun Ro, Jin Ho Song

Nuclear Technology / Volume 112 / Number 2 / Pages 181-193

November 1995

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Irradiation Performance of Fast Flux Test Facility Drivers Using D9 Alloy

A. L. Pitner, B. C. Gneiting, F. E. Bard

Nuclear Technology / Volume 112 / Number 2 / Pages 194-203

November 1995

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Choice of A Process Design for Simultaneous Detritiation and Upgrading of Heavy water for the Advanced Neutron Source

A. I. Miller, D. A. Spagnolo, J. R. DeVore

Nuclear Technology / Volume 112 / Number 2 / Pages 204-213

November 1995

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Taiwan Power Company’s Power Distribution Analysis and Fuel Thermal Margin Verification Methods for Pressurized Water Reactors

Ping-Hue Huang

Nuclear Technology / Volume 112 / Number 2 / Pages 214-226

November 1995

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Heat Transfer from A Plate Cooled by A Water Film with Countercurrent Air Flow

W. Ambrosini, A. Manfredini, F. Mariotti, F. Oriolo, P. Vigni

Nuclear Technology / Volume 112 / Number 2 / Pages 227-237

November 1995

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Thermal-Hydraulic Modeling and Severe Accident Radionuclide Transport

F. Oriolo, W. Ambrosini, G. Fruttuoso, F. Parozzi, R. Fontana

Nuclear Technology / Volume 112 / Number 2 / Pages 238-249

November 1995

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Probabilistic Analysis of Limiting Conditions for Operation Action Requirements Including Risk of Shutdown

T. Mankamo, I. S. Kim, P. K. Samanta

Nuclear Technology / Volume 112 / Number 2 / Pages 250-265

November 1995

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Development of the On-Line Operator Aid System OASYS Using A Rule-Based Expert System and Fuzzy Logic for Nuclear Power Plants

Soon Heung Chang, Ki Sig Kang, Seong Soo Choi, Han Gon Kim, Hee Kyo Jeong, Chul Un Yi

Nuclear Technology / Volume 112 / Number 2 / Pages 266-294

November 1995

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Transient Gap Conductance in Nuclear Fuel Rods

G. Dharmadurai

Nuclear Technology / Volume 112 / Number 2 / Pages 295-298

November 1995

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