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Volume 76

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

Development of a Postscram Analyzer for Boiling Water Reactors

Bill K.-H. Sun, Robert Colley, David G. Cain, John W. Hallam

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 352-359

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A33920

Experimental Studies of the Air Coolability of TRIGA Reactors Following a Loss-of-Coolant Accident

Mohamed S. El-Genk, Sung-Ho Kim, Galal M. Zaki, Jeffrey S. Philbin, James F. Schulze, Fabian C. Foushée

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 360-369

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33921

A Probabilistic Analysis Method to Evaluate the Effect of Human Factors on Plant Safety

Hiroshi Ujita

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 370-376

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33922

A Comparison of Measured Radionuclide Release Rates from Three Mile Island Unit-2 Core Debris for Different Oxygen Chemical Potentials

V. F. Baston, K. J. Hofstetter, Robert F. Ryan

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 377-389

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A33923

CANDU Pressurized Heavy Water Reactor Thorium-²³³U Oxide Fuel Evaluation Based on Optimal Fuel Management

Hugues W. Bonin

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 390-399

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT87-A33924

Gamma Radiation Effects on Time-Dependent Iodine Partitioning

Paul W. Marshall, Jeffrey B. Lutz, James L. Kelly

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 400-407

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT87-A33925

Radiography Experiments at Argonne National Laboratory

Wade J. Richards, Howard A. Larson

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 408-419

Technical Paper / Material / dx.doi.org/10.13182/NT87-A33926

Total Control Worth by Inspection

Charles R. Marotta

Nuclear Technology / Volume 76 / Number 3 / March 1987 / Pages 420-422

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT87-A33927

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