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Volume 84

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Number 1

Table of Contents
Authors(Chaung Lin, Jen-Min Chen, Shaw-Cuang Lee, Der-Jhy Shieh, Truong V. Vo, Michael S. Harris, Bryan F. Gore, Hsing Chien Yeh, William E. Kastenberg, Walter J. Karplus, Marco Cigarini, Mario Dalle Donne, Mano Subudhi, John H. Taylor, Marvin Sheets, Heinz Nabielek, Werner Schenk, Werner Heit, Alfred-Wilhelm Mehner, Daniel T. Goodin, Tapas C. Maiti, Monty R. Smith, Jagdish C. Laul, Donald G. Schweitzer, C.-K. Chris Wang, Thomas E. Blue, Reinhard Gahbauer, Charles Jacquemart,Mabruk Methnani,. Juan Jaliff, Sigurd Børresen, Adolfas K. Gaigalas, Ann Chidester Van Orden, Baldwin Robertson, Thomas H. Mareci, Lori A. Lewis)

Power Signal Validation for Taiwan Research Reactor

Chaung Lin, Jen-Min Chen, Shaw-Cuang Lee, Der-Jhy Shieh

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 7-13

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34191

Probabilistic Risk Assessment Based Inspection Guidance for Arkansas Nuclear One Unit 1

Truong V. Vo, Michael S. Harris, Bryan F. Gore

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 14-22

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34192

Applications of a Parallel Processing Modular Simulation System for Dynamic Simulation of Nuclear Power Plants

Hsing Chien Yeh, William E. Kastenberg, Walter J. Karplus

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 23-32

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34193

The Reflooding Phase After a Loss-of-Coolant Accident in an Advanced Pressurized Water Reactor

Marco Cigarini, Mario Dalle Donne

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 33-53

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34194

Testing of Electric Motors for Monitoring Age-Related Degradations

Mano Subudhi, John H. Taylor, Marvin Sheets

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 54-61

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34195

The Performance of High-Temperature Reactor Fuel Particles at Extreme Temperatures

Heinz Nabielek, Werner Schenk, Werner Heit, Alfred-Wilhelm Mehner, Daniel T. Goodin

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 62-81

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT89-A34196

Colloid Formation Study of U, Th, Ra, Pb, Po, Sr, Rb, and Cs in Briny (High Ionic Strength) Groundwaters: Analog Study for Waste Disposal

Tapas C. Maiti, MOnty R. Smith, Jagdish C. Laul

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 82-87

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT89-A34197

Inconsistencies in Thermodynamic Analyses of Long-Term Isolation of High-Level Waste

Donald G. Schweitzer

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 88-92

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT89-A34198

A Neutronic Study of an Accelerator-Based Neutron Irradiation Facility for Boron Neutron Capture Therapy

C.-K. Chris Wang, Thomas E. Blue, Reinhard Gahbauer

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 93-107

Technical Paper / Radioisotopes and Isotope Separation / dx.doi.org/10.13182/NT89-A34199

Experience with the On-Line Core Master Monitoring and Predicting System at Kernkraftwerk Leibstadt

Charles Jacquemart, Mabruk Methnani, Juan Jaliff, Sigurd Børresen

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 108-112

Technical Paper / Technique / dx.doi.org/10.13182/NT89-A34200

Application of Magnetic Resonance Imaging to Visualization of Flow in Porous Media

Adolfas K. Gaigalas, Ann Chidester Van Orden, Baldwin Robertson, Thomas H. Mareci, Lori A. Lewis

Nuclear Technology / Volume 84 / Number 1 / January 1989 / Pages 113-118

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT89-A34201

Number 2

Table of Contents
Authors(Chih Wu, David A. Petti, Kazuhiko Akamine, K. J. Hofstetter, V. F. Baston, Horng-Yu Wu, Ming-Yuan Hsiao, Anthony J. Baratta, Bernard R. Bandini, E. L. Tolman, Todd K. Campbell, Edgar Robert Gilbert, Cheryl Knox Thornhill, Bernard J. Wrona, A. A. Argekar, S. K. Thulasidas, M. J. Kulkarni, M. K. Bhide, R. Sampathkumar, S. V. Godbole, V. C. Adya, B. A. Dhawale, B. Rajeshwari, Neelam Goyal, P. J. Purohit, A. G. Page, A. G. I. Dalvi, T. R. Bangia, M. D. Sastry, P. R. Natarajan, J. T. Mihalczo, W. T. King)

Power Optimization of an Indirect Gas-Cooled Nuclear Reactor Plant

Chih Wu

Nuclear Technology / Volume 84 / Number 2 / February 1989 / Pages 123-127

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34182

Silver-Indium-Cadmium Control Rod Behavior in Severe Reactor Accidents

David A. Petti

Nuclear Technology / Volume 84 / Number 2 / February 1989 / Pages 128-151

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34183

Characterization of Suspended Particles in Three Mile Island Unit 2 Reactor Coolant Water

Kazuhiko Akamine, K. J. Hofstetter, V. F. Baston

Nuclear Technology / Volume 84 / Number 2 / February 1989 / Pages 152-168

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34184

Analysis of the Source Range Monitor During the First Four Hours of the Three Mile Island Unit 2 Accident

Horng-Yu Wu, Ming-Yuan Hsiao, Anthony J. Baratta, Bernard R. Bandini, E. L. Tolman

Nuclear Technology / Volume 84 / Number 2 / February 1989 / Pages 169-181

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT89-A34185

Oxidation Behavior of Spent UO₂ Fuel

Todd K. Campbell, Edgar Robert Gilbert, Cheryl Knox Thornhill, Bernard J. Wrona

Nuclear Technology / Volume 84 / Number 2 / February 1989 / Pages 182-195

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT89-A34186

Trace Metal Characterization of the U-AI Matrix by Atomic Spectroscopy

A. A. Argekar, S. K. Thulasidas, M. J. Kulkarni, M. K. Bhide, R. Sampathkumar, S. V. Godbole, V. C. Adya, B. A. Dhawale, B. Rajeshwari, Neelam Goyal, P. J. Purohit, A. G. Page, A. G. I. Dalvi, T. R. Bangia, M. D. Sastry, P. R. Natarajan

Nuclear Technology / Volume 84 / Number 2 / February 1989 / Pages 196-204

Technical Paper / Analyse / dx.doi.org/10.13182/NT89-A34187

Quality Assurance Verification of High-Flux Isotope Reactor Fuel Elements by the ²⁵²Cf-Source-Driven Noise Analysis Method

J. T. Mihalczo, W. T. King

Nuclear Technology / Volume 84 / Number 2 / February 1989 / Pages 205-223

Technical Paper / Techniques / dx.doi.org/10.13182/NT88-2

Number 3

Table of Contents
Authors(David P. Wagner, Larry A. Minton, John P. Gaertner, B. Thierry Meslin, Hymie Sol Shapiro, James Edward Smith, Yean-Chuan Yeh, Jyh-Tong Teng, David H. Worledge, Ian B. Wall, Hans J. Wingender, R. Leicht, Nathan Siu, Ali Mosleh, Michel Bloch, Daniel Dussarté, Jean-Louis Pierrey, Takeshi Matsuoka, Michiyuki Kobayashi, Kazuo Takemura, Henk W. Kalfsbeek, Shih-Kuei Cheng, Selim Sancaktar, David R. Sharp, B. John Garrick, Yukio Ishiguro, Keisuke Okumura, Corinne Bangil, Gerard Gambier, Michel Soldevila)
Introduction to Nuclear Radiation Detectors(Mary Gerry White)

Risk-Based Analysis Methods Applied to Nuclear Power Plant Technical Specifications

David P. Wagner, Larry A. Minton, John P. Gaertner

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 233-238

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34204

Analysis and Quantification of Common-Cause Failures on the Basis of Operating Experience

B. Thierry Meslin

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 239-246

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34205

Comparison Between Canadian Probabilistic Safety Assessment Methods Formulated by Atomic Energy of Canada Limited and Probabilistic Risk Assessment Methods

Hymie Sol Shapiro, James Edward Smith

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 247-251

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34206

Quantification of Dynamic Human Error Probabilities in Terms of Sampled Timing Data

Yean-Chuan Yeh, Jyh-Tong Teng

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 252-255

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34207

Overview of the Electric Power Research Institute Research Program on Common-Cause Failures

David H. Worledge, Ian B. Wall

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 256-259

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34208

A Modular Steady States Approach for Fuel Cycle Facility Probabilistic Risk Assessment

Hans J. Wingender, R. Leicht

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 260-264

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34209

Treating Data Uncertainties in Common-Cause Failure Analysis

Nathan Siu, Ali Mosleh

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 265-281

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34210

Probabilistic Risk Assessment Related to Multiple Ruptures of Steam Generator Tubes

Michel Bloch, Daniel Dussarté, Jean-Louis Pierrey

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 282-284

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34211

The GO-FLOW Methodology: A Reliability Analysis of the Emergency Core Cooling System of a Marine Reactor Under Accident Conditions

Takeshi Matsuoka, Michiyuki Kobayashi, Kazuo Takemura

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 285-295

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34212

The Use of Abnormal Event Data in Nuclear Power Reactor System Analysis Using the Sequence Combining Method

Henk W. Kalfsbeek

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 296-304

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34213

Seal Loss-of-Coolant Accident and Recovery Actions Following Loss of Component Cooling Water

Shih-Kuei Cheng

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 305-314

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34214

Use of Probabilistic Risk Assessment and Economic Risk at the Plant Design Stage: An Application

Selim Sancaktar, David R. Sharp

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 315-318

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34215

Lessons Learned from 21 Nuclear Plant Probabilistic Risk Assessments

B. John Garrick

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 319-330

Technical Paper / Probabilistic Safety Assessment and Risk Management / Nuclear Safety / dx.doi.org/10.13182/NT89-A34216

Pancake Core High Conversion Light Water Reactor Concept

Yukio Ishiguro, Keisuke Okumura

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 331-343

Technical Paper / Probabilistic Safety Assessment and Risk Management / Fission Reactor / dx.doi.org/10.13182/NT89-A34217

Four-Batch Fuel Management with Plutonium Recycling

Corinne Bangil, Gérard Gambier, Michel Soldevila

Nuclear Technology / Volume 84 / Number 3 / March 1989 / Pages 344-349

Technical Paper / Probabilistic Safety Assessment and Risk Management / Fuel Cycle / dx.doi.org/10.13182/NT89-A34218