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Institute of Social Research Articles

Characteristics of Self-Rating and Rating by Others of Safety Behavior
A Fundamental Study on the Influence of the Illuminant Conditions for the Visibility
Reduction of Noise Influence during the Periodical Inspection of the Nuclear Power Plant
Attitude of Students Intending to be Teachers Toward Nuclear Power Generation and the Environment
The Effect of Energy-Saving Information on Households’ Energy Consumption Behavior

Institute of Nuclear Technology Articles

Analysis of Convergence of Uncertainty and Important Factors Affecting Uncertainty in Level 1 PSA for Pressurized Water Reactors
Experiments and Numerical Simulations of Fluctuating Thermal Stratification in a Branch Pipe
Experiment of Cavitation Erosion at the Exit of a Long Orifice
Numerical Analysis of Gas-Liquid Two-Phase Flow in Secondary Side of Steam Generator
Influence of Dissolved Hydrogen and Temperature on Primary Water Stress Corrosion Cracking of Mill Annealed Alloy 600
SCC Susceptibility Evaluation of Plastic Deformed Austenitic Stainless Steels
Influence of Temperature, Hydrogen and Boric Acid Concentration on IGSCC Susceptibility of Unsensitized 316 Stainless Steel
Structural Analysis of Surface Film on Alloy 600 Formed under Environment of PWR Primary Water
Effect of Elastic Anisotropy of Crystal Grain on Stress Intensity Factor
Effects of Material Property Changes on Irradiation Assisted Stress Corrosion Cracking
Radiation Field Analyses in Reactor Vessels of PWRs
Characterization of SCC Crack Tips and Surface Oxide Layers in Alloy 600
Grain Boundary Phosphorus Segregation under Thermal Aging in Low Alloy Steels
Fatigue Damage Evaluation of Stainless Steel Pipes in Nuclear Power Plants Using Positron Annihilation Lineshape Analysis
Quantification of a Decision-making Failure Probability of the Accident Management Using Cognitive Analysis Model
Efficient Improvement of Nuclear Power Plant Safety by Reorganization of Risk-Informed Safety Importance Evaluation Methods for Piping Welded Portions

Document

Investigation and Analysis of Hydrogen Ignition and Explosion Events in Foreign Nuclear Power Plants
Review and Analysis for Events of Damage of Electric Circuits for Safe Shutdown in Postulated Fires at PWR Power Plants and Countermeasures for Preventing Loss of Inventory Water Caused by Malfunction of Valves
Application of Ultrasonic Testing Technique to Detect Gas Accumulation in Important Pipings for Pressurized Water Reactors Safety
Development of an Autoclave with Zirconia Crystal Windows for In-Situ Observation of Sample Surface under Primary Water Conditions of Pressurized Water Reactors

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