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Volume 76

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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

Number 2

Table of Contents
Authors(John C. Lee, Sin Tao Hsue, Mukesh Tayal, Ed Mischkot, Harve E. Sills, A. W. L. Segel, Masanori Takahashi, Masayuki Muroi, Atsuyuki Inoue, Masahiro Aoki, Makoto Takizawa, Kenkichi Ishigure, Norihiko Fujita, Kune Yull Suh, Neil E. Todreas, Pao-Shu Chang, Yau-Hui Ho, Chien Chung, Liq-Ji Yuan, Pao-Shan Weng, Tunc Aldemir, Steven A. Arndt, Don W. Miller, Alan B. Harker, John F. Flintoff, Peter J. Jensen, James F. Lang, Jason Chao, Peter J. Jensen, Kent D. Richert, Jason Chao, Thomas J. Downar)
Low Probability/High Consequence Risk Analysis—Issues, Methods and Case Studies(Gerald A. Schlapper)
Reliability Engineering for Nuclear and Other High Technology Systems(Gerald A. Schlapper)
Thorium Dioxide: Properties and Nuclear Applications(Geoffrey G. Eichholz)
Guidebook to Light Water Reactor Safety Analysis(Raymond L. Murray)
Nuclear Energy—A Sensible Alternative(Gerald A. Schlapper)
Introductory Nuclear Reactor Dynamics(David L. Hetrick)

Determination of Isotopic Ratios from Fuel Burnup

John C. Lee, Sin Tao Hsue

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 203-208

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT87-A33874

ELOCA-A: A Code for Radial and Axial Behavior of CANDU Fuel Elements at High Temperatures

Mukesh Tayal, Ed Mischkot, Harve E. Sills, A. W. L. Segel

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 209-220

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT87-A33875

Properties of Bentonite Clay as Buffer Material in High-Level Waste Geological Disposal. Part I: Chemical Species Contained in Bentonite

Masanori Takahashi, Masayuki Muroi, Atsuyuki Inoue, Masahiro Aoki, Makoto Takizawa, Kenkichi Ishigure, Norihiko Fujita

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 221-228

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33876

An Experimental Correlation of Cross-Flow Pressure Drop for Triangular Array Wire-Wrapped Rod Assemblies

Kune Yull Suh, Neil E. Todreas

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 229-240

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33877

In Vivo Measurement of Organ Mercury by Prompt Gamma Activation Analysis Using a Mobile Nuclear Reactor

Pao-Shu Chang, Yau-Hui ho, Chien Chung, Liq-Ji Yuan, Pao-Shan Weng

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 241-247

Technical Paper / Analyse / dx.doi.org/10.13182/NT87-A33878

Simulation of the Transient Response of Ionization Chambers to Bias Voltage Perturbations

Tunc Aldemir, Steven A. Arndt, Don. W. Miller

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 248-259

Technical Paper / Technique / dx.doi.org/10.13182/NT87-A33879

The Formation of Surface Layers and Reaction Products in the Leaching of Defense Borosilicate Nuclear Waste Glass

Alan B. Harker, John F. Flintoff

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 263-275

Performance of Borosilicate Glass High-Level Waste Forms in Disposal Systems / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A33880

A Guillotine Tube Rupture Modeling Technique Using RETRAN-02

Peter J. Jensen, James F. Lang, Jason Chao

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 279-289

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33881

A Parametric Study of an Anticipated Transient Without Scram in a Westinghouse Four-Loop Plant

Peter J. Jensen, Kent D. Richert, Jason Chao

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 290-302

Fourth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A33882

Moderator Feedback Effects in Two-Dimensional Nodal Methods for Pressurized Water Reactor Analysis

Thomas J. Downar

Nuclear Technology / Volume 76 / Number 2 / February 1987 / Pages 303-307

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT87-A33883

Number 3

Table of Contents
Authors(David P. Chan, David L. Larkin, Kazuo Azekura, Kikuo Umegaki, Kotaro Inoue, Sang K. Rhow, James E. McElroy, Dennis M. Switick, Constantine P. Tzanos, Bill K.-H. Sun, Robert Colley, David G. Cain, John W. Hallam, Mohamed S. El-Genk, Sung-Ho Kim, Galal M. Zaki, Jeffrey S. Philbin, James F. Schulze, Fabian C. Foushée, Hiroshi Ujita, V. F. Boston, K. J. Hofstetter, Robert F. Ryan, Hugues W. Bonin, Paul W. Marshall, Jeffrey B. Lutz, James L. Kelly, Wade J. Richards, Howard A. Larson, Charles R. Marotta)
Treatise on Heavy Ion Science(Bernard L. Cohen)

Finite Element Analysis of Boiling Water Reactor Fuel Channel Bulge and Bow

David P. Chan, David L. Larkin

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 319-324

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33917

An Analysis of Initiating and Transition Phases for an Unprotected Loss-of-Flow Accident in an Axially Heterogeneous Fast Breeder Reactor Core

Kazuo Azekura, Kikuo Umegaki, Kotaro Inoue, Sang K. Rhow, James E. McElroy, Dennis M. Switick

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 325-336

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33918

Liquid-Metal Fast Breeder Reactor Intermediate Heat Exchanger Transient Modeling for Faster Than Real-Time Analysis

Constantine P. Tzanos

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 337-351

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33919