ホームabout INSSINSS JournalINSS Journal 2006 Vol.13 INSS Journal 2006 Vol.13 back to INSS Journal＞＞ Institute of Social Research Articles Measurement and evaluation of human factor training in nuclear power plantsThe Influence Nuclear Power has on Corporate Image and the Effect of offering Merit Information of Nuclear PowerSocial Awareness on Nuclear Fuel CycleSituation of Energy and Environmental Education in GermanyAwareness 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 OrificeEvaluation of Local Stress at Grain Boundaries by Three-Dimensional Polycrystalline ModelMicrostructural evolution in low alloy steels under high dose ion irradiationDeformation Structure in Stainless Steels Irradiated in a PWRInfluence of Water Chemistry on IGSCC Susceptibility and Crack Growth Rate of SUS 316 in High-Temperature WaterPotential dependencies on IGSCC growth of non-sensitized stainless steels in high temperature water and role of Grain Boundary Creep on IGSCC Initiation and PropagationStress 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 driveExamination of Applicability of Thermoelectric Power Measurement for Thermal Aging Evaluation of Cast Duplex Stainless Steel to Real Components in Nuclear Power PlantsDevelopment of Depth Measurement Technique for Flaws in Stainless Steel Weld Zones with A Twin Matrix Array Ultrasonic TransducerDevelopment of Measurement Technique for Crack Depth in Weld Zone of Thick Stainless Steel Pipe with Ultrasonic Phased Array TOFDNew Method of Classifying Causes, including Aging and Human Error, of Events Which Occurred at Nuclear Power PlantsTrend Analysis and Comparison of Operators’ Human Error Events Occurred at Overseas and Domestic Nuclear Power PlantsTrend Analysis of Air Operated Valve Positioner Failure Events at Nuclear Power PlantsEvents Analysis of the Main Generator Using Reliability Block DiagramTrend Analysis of Breaker Events at United States Nuclear Power PlantsComparison of Secondary-piping Wear Management at Nuclear Power Plants in Japan and Other CountriesImprovement 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
