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Institute of Social Research Articles

A Proposal for Human Factors Education in a Power Plant Company
Effects of a power shortage in the Tokyo Metropolitan area on awareness of nuclear power generation and power savings behavior
Effectiveness of transmitting safety-measures information in risk communication of nuclear power generation. – evaluation by the receiver of the messages –
Recognition of People with an Opinion that Nuclear Power Generation causes Global Warming
Trial Encouraging the Children to Like Science: Activities of a Science Education Study Group with the Participation of Science Teachers in Fukui Prefecture

Institute of Nuclear Technology Articles

Analysis of Adverse Events occurred at Overseas Nuclear Power Plants in 2003
A Probabilistic Safety Assessment Approach toward Identification of Information on Safety Significant Adverse Events at Overseas Nuclear Power Plants
New Classification of Operators’ Human E rrors at Overseas Nuclear Power Plants and Preparation of Easy-to-Use Case Sheets.
Improvement of Condition-Based Maintenance Technology by Utilization of Thermography
Evaluation of Seismic Characteristic of Cylindrical Water Storage Tank by Vibration Test － Dependence of Dynamic Fluid Pressure Distribution on Input Acceleration －
Investigation of Detection Method of Cavitation Behavior with Accelerometer and AE sensor Mounted on Outer Surface of Piping
Influence of Minor Elements (Ti, Nb) on Primary Water Stress Corrosion Cracking of Alloy 600
Influence of Temperature and Water Chemistry on IGSCC Susceptibility of SUS316 in High-Temperature Water
Influence of Water Chemistry Conditions and Cr Concentration on Oxide Film of SUS316 under High Temperature Water
Measurement of Plastic Strain of Polycrystalline Material by Electron Backscatter Diffraction
Characterization of matrix damage in ion-irradiated reactor vessel steel
Detection Sensitivity and Sizing Ability of Defects in Cast Stainless Steel with Newly Developed Automatic Ultrasonic Inspection System
Development of Ultrasonic Testing T echnique with the Large Transducer to Inspect the Containment Vessel plates of Nuclear Power Plant Embedded in Concrete
Influence of Carbon, Phosphorus and Sulfur on Thermoelectric Power of Fe-Cr-Ni Alloys
Evaluation of Nuclear Data for Emergency Preparedness System of Nuclear Power Plants －Comparison of Radioactivity Inventories by Newest Nuclear Data and Rather Older Nuclear Data－
Improvement of Dose Evaluation System for Employees at Severe Accident of Nuclear Power Plant － Development of Gamma-Ray Buildup Factors by Invariant Embedding Method and Application to Deep Penetration Problem by QAD Code and G33 Code －
Development of Iodine Analysis Codes for Chemical and Mass Transport Behavior under Severe Accident Condition and Their Application to International Standard Problem No.41
Improvement of Heat Transfer Models for Gap Cooling
Validation of Heat Transfer Models for Gap Cooling
Reflux Condensation Heat Transfer of Steam-Air Mixture under Gas-Liquid Countercurrent Flow

Document

Development of Assessment System for Tank Earthquake-Proof Design (ASTEP Code) Installing Automatic Operation and Knowledge Database
Evaluation of Maintenance Methods of PWR Primary System Pipes Based on PFM

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