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Institute of Social Research Articles

Measurement and evaluation of human factor training in nuclear power plants
The Influence Nuclear Power has on Corporate Image and the Effect of offering Merit Information of Nuclear Power
Social Awareness on Nuclear Fuel Cycle
Situation of Energy and Environmental Education in Germany
Awareness structure of the people with opinion that nuclear power is effective for preventing global warming

Institute of Nuclear Technology Articles

Evaluation of Seismic Characteristics of Cylindrical Water Storage Tank by Vibration Test (3 rd Report) －Nonlinear Vibration Response in Large Input Excitation and Consideration for its Generation Mechanism－
An approach for integrated evaluation method of thermal fatigue I -Application to thermal stratification of a closed branch pipe-
An Approach of Integrated Evaluation Method for Thermal Fatigue II － A Validation of Evaluation Method by Numerical Simulations －
Detection of Cavitation Behavior using Accelerometer and Microphone outside of Piping at Orifice
Evaluation of Local Stress at Grain Boundaries by Three-Dimensional Polycrystalline Model
Microstructural evolution in low alloy steels under high dose ion irradiation
Deformation Structure in Stainless Steels Irradiated in a PWR
Influence of Water Chemistry on IGSCC Susceptibility and Crack Growth Rate of SUS 316 in High-Temperature Water
Potential dependencies on IGSCC growth of non-sensitized stainless steels in high temperature water and role of Grain Boundary Creep on IGSCC Initiation and Propagation
Stress Corrosion Cracking of Stainless Steel under Deaerated High-Temperature Water － Influence of Cold Work and Processing Orientation －
Stress Corrosion Cracking of Stainless Steel under Deaerated High-Temperature Water － Influence of Grain Boundary Carbide Precipitation －
Mechanistic Study on SCC Crack Propagation of Welded Ni based Alloy － Phase 1 －
Life prediction of diaphragm material for air operation valve drive
Examination of Applicability of Thermoelectric Power Measurement for Thermal Aging Evaluation of Cast Duplex Stainless Steel to Real Components in Nuclear Power Plants
Development of Depth Measurement Technique for Flaws in Stainless Steel Weld Zones with A Twin Matrix Array Ultrasonic Transducer
Development of Measurement Technique for Crack Depth in Weld Zone of Thick Stainless Steel Pipe with Ultrasonic Phased Array TOFD
New Method of Classifying Causes, including Aging and Human Error, of Events Which Occurred at Nuclear Power Plants
Trend Analysis and Comparison of Operators’ Human Error Events Occurred at Overseas and Domestic Nuclear Power Plants
Trend Analysis of Air Operated Valve Positioner Failure Events at Nuclear Power Plants
Events Analysis of the Main Generator Using Reliability Block Diagram
Trend Analysis of Breaker Events at United States Nuclear Power Plants
Comparison of Secondary-piping Wear Management at Nuclear Power Plants in Japan and Other Countries
Improvement of Dose Evaluation System for Employees at Severe Accident in a Nuclear Power Plant －Introduction of the Dose Rate Conversion Coefficient & Addition of the Access Route Edit Function－

Document

Longitudinal survey of public opinion toward nuclear power generation; The result of a survey conducted one year after the Mihama Unit 3 accident

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