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Volume 92

Number 2

Table of Contents
Authors(Chien Chung, Chen-Yi Chen, Robert M. Edwards, Kwang Y. Lee, M. A. Schultz, Robert E. Kurth, David C. Cox, K. Sathyanarayana, Donald M. Ogden, Bernd Grambow, R. S. Forsyth, Lars O. Werme, Jordi Bruno, Michael D. Allen, Harlan W. Stockman, Kenneth O. Reil, Arthur J. Grimley, Ernst Warnecke, Dietmar Bröcking, Peter Podewils, Masanori Takahashi, Tatsuo Izumida, Fumio Kawamura, Hideo Yusa, S. Rajendran Pillai, R. Ranganathan, Cherian K. Mathews, John C. Statharas, John G. Bartzis, Demosthenes D. Papailiou, Hideo Nagasaka, Takashi Sato, Hirohide Oikawa, Ryoichi Hamazaki, Kenji Arai, Takao Kageyama, Hiroyuki Yoshida, Hiroshi Machiba, D. P. Pande, P. L. Dhar, R. S. Agarwal, R. V. Amalraj, M. N. Agu)

Modification of a Mobile Nuclear Reactor for Medical Diagnosis

Chien Chung, Chen-Yi Chen

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 159-166

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34467

State Feedback Assisted Classical Control: An Incremental Approach to Control Modernization of Existing and Future Nuclear Reactors and Power Plants

Robert M. Edwards, Kwang Y. Lee, M. A. Schultz

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 167-185

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT90-A34468

A Random Sampling Discrete Probability Algorithm with Condensation for Probabilistic Analysis

Robert E. Kurth, David C. Cox

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 186-193

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34469

RELAP5/MOD2 Analysis of N Reactor Cold-Leg Manifold Break Transient Without Scram

K. Sathyanarayana, Donald M. Ogden

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 194-203

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT90-A34470

Fission Product Release from Spent UO₂ Fuel Under Uranium-Saturated Oxic Conditions

Bernd Grambow, R. S. Forsyth, Lars O. Werme, Jordi Bruno

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 204-213

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34471

Fission Product Release and Fuel Behavior of Irradiated Light Water Reactor Fuel Under Severe Accident Conditions: The ST-1 Experiment

Michael D. Allen, Harlan W. Stockman, Kenneth O. Reil, Arthur J. Grimley

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 214-228

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT90-A34472

Guidelines for Quality Assurance and Quality Control of Radioactive Wastes

Ernst Warnecke, Dietmar Bröcking, Peter Podewils

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 229-237

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34473

Modeling on Evaporation Characteristics of a Reprocessing Plant High-Level Liquid Waste Concentrator

Masanori Takahashi, Tatsuo Izumida, Fumio Kawamura, Hideo Yusa

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 238-242

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT90-A34474

Studies of the Decomposition of Sodium Carbonate in High-Temperature Sodium

S. Rajendran Pillai, R. Ranganathan, Cherian K. Mathews

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 243-247

Technical Paper / Material / dx.doi.org/10.13182/NT90-A34475

Heat Transfer Modeling in Low Flows and Application to Reflood Heat Transfer

John C. Statharas, John G. Bartzis, Demosthenes D. Papailiou

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 248-259

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34476

Study of a Natural-Circulation Boiling Water Reactor with Passive Safety

Hideo Nagasaka, Takashi Sato, Hirohide Oikawa, Ryoichi Hamazaki, Kenji Arai, Takao Kageyama, Hiroyuki Yoshida, Hiroshi Machiba

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 260-268

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34477

Thermal Hydraulics During Boiling in Thermosyphon Evaporators

D. P. Pande, P. L. Dhar, R. S. Agarwal, R. V. Amalraj

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 269-281

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34478

An Empirical Calculational Procedure for Beta-Particle Escape Efficiency in Delayed Self-Powered Neutron Detectors

M. N. Agu

Nuclear Technology / Volume 92 / Number 2 / November 1990 / Pages 282-283

Technical Note / Analyse / dx.doi.org/10.13182/NT90-A34479

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