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Volume 79

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Number 1

  • Table of Contents
  • Author List(Edmund T. Rumble, Boyer B. Chu, Yigal Ronen, Melvin J. Leibson, Douglas R. Smith, Robert W. Albrecht, Sreenivas Jayanti, Richard N. Christensen, Nancy Yost, Chris Wang, David van Deusen, Don W. Miller, Corwin L. Atwood, Raymond C. Lloyd, E. Duane Clayton, Robert E. Wilson, Robert C. McBroom, Robert R. Jones, Heinz Peter Berg, Dietrich Ehrlich, Heinrich Illi, Bruno R. Thomauske, Tzing-Shenq Horng, Cheng-Chang Chieng, Mrs. Abdul Majeed Shakila, Thandangorai Ganapathi Srinivasan, Kanwal Nain Sabharwal, Polur Rangarao Vasudeva Rao, Yasushi Takeda)

An Approach for Integrating Plant Operations and Maintenance Information with System Reliability Analysis

Edmund T. Rumble, Boyer B. Chu

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 7-19

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A16001

The Multispectrum High Convertor Water Reactor

Yigal Ronen, Melvin J. Leibson

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 20-34

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A16002

A Resonant Cavity Level Measurement Technique for Use with Gas Enhancement Modules in Liquid-Metal Reactors

Douglas R. Smith, Robert W. Albrecht

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 35-50

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A16003

Preliminary Analysis of a Small, Inherently Safe Boiling Water Reactor

Sreenivas Jayanti, Richard N. Christensen, Nancy Yost, Chris Wang, David van Deusen, Don W. Miller

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 51-65

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A16004

Distributions for Binomial Failure Rate Parameters

Corwin L. Atwood

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 66-81

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A16005

Critical Experiments Using High-Enriched Uranyl Nitrate with Cadmium Absorber

Raymond C. Lloyd, E. Duane Clayton, Robert E. Wilson, Robert C. McBroom, Robert R. Jones

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 82-91

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A16006

Safety Analyses and Derivation of Site-Specific Requirements on Radioactive Waste for the Planned German Repository “Konrad”

Heinz Peter Berg, Dietrich Ehrlich, Heinrich Illi, Bruno R. Thomauske

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 92-99

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A16007

Numerical Investigation of Fluid and Thermal Mixing During High-Pressure Injection

Tzing-Shenq Horng, Cheng-Chang Chieng

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 100-115

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A16008

Dissolution of PuO2 in HNO3-HF-N2H4 Medium

Mrs. Abdul Majeed Shakila, Thandangorai Ganapathi Srinivasan, Kanwal Nain Sabharwal, Polur Rangarao Vasudeva Rao

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 116-119

Technical Note / Chemical Processing / dx.doi.org/10.13182/NT87-A16009

Measurement of Velocity Profile of Mercury Flow by Ultrasound Doppler Shift Method

Yasushi Takeda

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Pages 120-124

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A16010

The Politics of Uranium

Mary Gerry White

Nuclear Technology / Volume 79 / Number 1 / October 1987 / Page 125

Department / Book Review / dx.doi.org/10.13182/NT87-A16011

Number 2

HTR-100 Industrial Nuclear Power Plant for Generation of Heat and Electricity

Siegfried Brandes, Wolfgang Kohl

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 135-143

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34031

Design Principles of a Simple and Safe 200-MW(thermal) Nuclear District Heating Plant

Claus Goetzmann, Dietmar Bittermann, Andreas Göbel

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 144-157

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34032

Assessment of Safety-Relevant Aspects of Kraftwerk Union’s 200-MW(thermal) Nuclear District Heating Plant Concept

Peter Erlenwein, Willi Frisch, Peter Kafka, Rudolf E. Kirmse, Siegfried Langenbuch

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 158-166

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34033

The Swiss Heating Reactor for District Heating of Small Communities

Peter Burgsmüller, Andreas Jacobi, Jr., Jean-François Jaeger, Max J. Kläntschi, Walter Seifritz, François Vuilleumier, Ferdinand Wegmann

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 167-174

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34034

The SECURE Heating Reactor

Christen Pind

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 175-185

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34035

Design and Testing of the Reactor-Internal Hydraulic Control Rod Drive for the Nuclear Heating Plant

Pramod Batheja, Werner Jakob Meier, and, Peter Josef Rau

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 186-195

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34036

Optimization of Fuel Exchange Machine Operation for Boiling Water Reactors Using an Artificial Intelligence Technique

Koichi Sekimizu, Tsuneyasu Araki, Shin-Ichiro Tatemichi

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 196-209

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34037

Caorso Limit Cycle Oscillation Analysis with Three-Dimensional Transient Code TOSDYN-2

Yukio Takigawa, Yutaka Takeuchi, Shigeaki Tsunoyama, Shigeo Ebata, Kai C. Chan, Carlo Tricoli

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 210-227

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34038

Probabilistic Fracture Evaluation of a Fast Breeder Reactor Cover

Sadao Hattori, Norihiko Handa

Nuclear Technology / Volume 79 / Number 2 / November 1987 / Pages 228-240

Technical Paper / Nuclear Power Plants for Generation of Heat / Fission Reactor / dx.doi.org/10.13182/NT87-A34039

Number 3

  • Table of Contents
  • Authors(William M. Davidson, Alan K. Morimoto, Mary M. Moya, J. Lee Schoeneman, Siegfried Thunborg, Gregory P. Starr, Samir M. Sami, C. Tran, Mo-chen Hsu, Norio Naito, Akira Sakuma, Kei Shigeno, Nobuyuki Mori, Jae-Joo Ha, Tunc Aldemir, Fahmy M. Hussein, Mohamed A. Obeid, Khalid S. El-Malahy, Stephen E. Binney, Richard D. Harris, Tatsuhiko Uda, Yoshihiro Ozawa, Hajime Iba, Hans Wanner, Othar K. Tallent, Earl W. McDaniel, Karen E. Dodson, Terry T. Godsey, Alexander P. Murray, Carol Braester, Roger Thunvik, Hyong Chol Kim, Ming-Yuan Hsiao, Samuel H. Levine)
  • Technical Reviewers

A Remote Maintenance Robot System for a Pulsed Nuclear Reactor

William M. Davidson, Alan K. Morimoto, Mary M. Moya, J. Lee Schoeneman, Siegfried Thunborg, Gregory P. Starr

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 249-259

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A34015

A Digital Computer Model for Predicting Reactor Coolant Pump Behavior

Samir M. Sami, C. Tran

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 260-273

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A34016

Prompt-Neutron Decay Constant Estimation at Full-Power Operation

Mo-Chen Hsu

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 274-283

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A34017

A Real-Time Expert System for Nuclear Power Plant Failure Diagnosis and Operational Guide

Norio Naito, Akira Sakuma, Kei Shigeno, Nobuyuki Mori

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 284-296

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A34018

Pool Dynamics of Natural-Convection-Cooled Research Reactors

Jae-Joo Ha, Tunc Aldemir

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 297-310

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT87-A34019

Site Selection of a Dual Purpose Nuclear Power Plant in Saudi Arabia

Fahmy M. Hussein, Mohamed A. Obeid, Khalid S. El-Malahy

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 311-321

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT87-A34020

Calculational Assessment of the Measurability of Key Radionuclides for Severely Failed Nuclear Power Plant Fuel

Stephen E. Binney, Richard D. Harris

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 322-327

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT87-A34021

Melting of Uranium-Contaminated Metal Cylinders by Electroslag Refining

Tatsuhiko Uda, Yoshihiro Ozawa, Hajime Iba

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 328-337

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A34022

Modeling Interaction of Deep Groundwaters with Bentonite and Radionuclide Speciation

Hans Wanner

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 338-347

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A34023

Empirical Correlations from Waste Grout Formulation Data

Othar K. Tallent, Earl W. McDaniel, Karen E. Dodson, Terry T. Godsey

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 348-358

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A34024

Mathematical Modeling of the Chemical Decontamination of Boiling Water Reactor Components

Alexander P. Murray

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 359-370

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT87-A34025

A Study of Flow Through a Fracture Network Described by Statistically Distributed Properties

Carol Braester, Roger Thunvik

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 371-376

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT87-A34026

A Design of the Liquid-Metal Reactor Having an Almost Constant Reactivity

Hyong Chol Kim, Ming-Yuan Hsiao, Samuel H. Levine

Nuclear Technology / Volume 79 / Number 3 / December 1987 / Pages 377-381

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT87-A34027