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Volume 76

Number 1

Table of Contents
Authors(U. S. Rohatgi, Pradip Saha, V. K. Chexal, Jong Ho Lee, Soon Heung Chang, U. S. Rohatgi, Christine Yuelys-Miksis, Pradip Saha, Harald Moers, Hanns Klewe-Nebenius, Hans J. Ache, Pao-Shan Weng, Hseuh-Hsing Cheng, Chuan-Chung Hsu, Kuan-Han Sun, Jeffery David Lewins, Tsunetaka Banba, Takashi Murakami, Hideo Kimura, Lance J. Agee, Thomas L. Temple, Terry J. Garrett, Steven W. Sorrell, Jason Chao, William H. Layman, Gary Vine, Robert O. Montgomery, Kenneth L. Peddicord, Roger L. Boyer, Charles R. Albury, Lance G. Riniker, Kevin B. Ramsden, Laurence M. Olson, Trevor L. Cook, Steven M. Mirsky, Bruce Ching, Chong Chiu, Jason Chao, William H. Layman, Gary Vine, Charles W. Forsberg)
A Perspective on Chernobyl(Milt Levenson)
Comments on “Feasibility of Once-Through Thorium Fuel Cycle for Candu Reactors”(Michael Milgram)
Comments on “Radiation Protection Practices and Experience in French Operating Reactors”(J. P. Van Berlo)
Reply to “Comments on ‘Radiation Protection Practices and Experience in French Operating Reactors’”(André Gauvenet)
Textbook of Nuclear Medicine(Raymond L. Murray)
The Nuclear Suppliers and Nonproliferation(John A. Wethington, Jr.)

Considerations for Realistic Emergency Core Cooling System Evaluation Methodology for Light Water Reactors

U. S. Rohatgi, Pradip Saha, V. K. Chexal

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 11-26

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33893

An On-Line Pressurizer Surveillance System Design to Prevent Small-Break Loss-of-Coolant Accidents Through Power-Operated Relief Valves Using a Microcomputer

Jong Ho Lee, Soon Heung Chang

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 27-40

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33894

Determination of Appendix K Conservatisms for Westinghouse Pressurized Water Reactors Using TRAC-PD2/MOD1

U. S. Rohatgi, Christine Yuelys-Miksis, Pradip Saha

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 41-50

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33895

X-Ray Photoelectron Spectroscopy and Electron Probe X-Ray Microanalysis Investigation and Chemical Speciation of Aerosol Samples Formed in Light Water Reactor Core-Melting Experiments

Harald Moers, Hanns Klewe-Nebenius, Hans J. Ache

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 51-59

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33896

The Applications of Nuclear Technology in Reactor Siting

Pao-Shan Weng, Hseuh-Hsing Cheng, Chuan-Chung Hsu, Kuan-Han Sun

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 60-67

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33897

In-Core Fuel Cycle Transients

Jeffery David Lewins

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 68-83

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT87-A33898

The Leaching Behavior of a Glass Waste Form—Part III: The Mathematical Leaching Model

Tsunetaka Banba, Takashi Murakami, Hideo Kimura

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 84-90

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33899

RETRAN Overview

Lance J. Agee

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 91-97

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33900

RETRAN Generic Review—A Retrospection

Thomas L. Temple

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 98-104

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33901

The Development and Application of System Analysis at Kansas Gas and Electric Company

Terry J. Garrett, Steven W. Sorrell

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 105-112

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33902

Reducing Scram Frequency by Modifying Reactor Setpoints for a Westinghouse Four-Loop Plant

Jason Chao, William H. Layman, Gary Vine

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 113-125

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33903

Nodalization Study of the Westinghouse Model E Steam Generator Secondary Side

Robert O. Montgomery, Kenneth L. Peddicord, Roger L. Boyer, Charles R. Albury

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 126-136

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33904

RETRAN Modeling of the Westinghouse Model D Steam Generator

Lance G. Riniker, Kevin B. Ramsden

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 137-142

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33905

RETRAN Analysis of Susquehanna Steam Electric Station Unit 2 Moisture Separator Drain Tank Level Transient Response

Laurence M. Olson

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 143-165

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33906

A Comparison of RETRAN-02 and TRAC-PF1 Simulations of a Loss of Off-Site Power Cooldown to Residual Heat Removal Entry Conditions at Calvert Cliffs Nuclear Power Plant

Trevor L. Cook, Steven M. Mirsky

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 166-171

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33907

Safety Analyses Using RETRAN-02 with Relaxed Trip Setpoints on Combustion Engineering Reactors

Bruce Ching, Chong Chiu, Jason Chao, William H. Layman, Gary Vine

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 172-184

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33908

Passive Emergency Cooling Systems for Boiling Water Reactors (PECOS-BWR)

Charles W. Forsberg

Nuclear Technology / Volume 76 / Number 1 / January 1987 / Pages 185-192

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT87-A33909

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