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Volume 84

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