Institute of Social Research Articles

• Surveyon maintenance skills required for nuclear power plant periodic inspections
• Skills ofPatrolling Inspection in Reports on Trouble Detection Cases in Substations
• An Opinion Survey on the Image of Incidents or Accidents at a Final Disposal Site for High-Level Radioactive Waste
• Activities of Energy and Environmental Education surrounding Kyoto Area ;Development of Teaching Models and the Role of Corporate Support

Institute of Nuclear Technology Articles

• Evaluation of Seismic Characteristics of Cylindrical Water Storage Tank by Vibration Test（5th Report） ―Proposal of a New Dynamic Buckling Analysis Method―
• The Effect of Local Flow Field on Flow Accelerated Corrosion − The Background of the Research and Measurements of Corrosion Rate after an Orifice−
• Development of Method to Measure Vibrational Stress of Small-Bore Piping with Multiple Contactless Displacement Sensors ―Examination of Applicability by Vibration Test Using a Pipe―
• CrackEmbryo Formation before CrackInitiation and Growth in High Temperature Water
• Primary Coolant Leakage Path Research of Reactor Vessel Head Penetration
• Mechanistic Study on SCC Propagation of Welded Nickel based Alloy,（IV） ― Influence of Dissolved Hydrogen on Crack Tips ―
• Role of Intergranular Oxidation on PWSCC of Nickel Based Alloys
• IASCC Crack-tip Observation in Irradiated Stainless Steels
• Fracture Behavior of Highly Irradiated Stainless Steels
• Microstructural Evolution in Low Alloy Steels after High Dose Ion Irradiation（2）
• Interaction between Slips and Damage structures in Ion-irradiated Stainless Steels
• Mechanism and Influence of Evolution of Crack Network under Thermal Fatigue Loading
• Effect of Cr content, hardness and micro structure on flow-accelerated corrosion in carbon steel pipes -Examination of replaced carbon steel pipes-
• Thermal Analysis of system composed of a specimen and a device for thermoelectric power measurement
• Study on the Ageing Degradation Diagnosis of Electric Cables Based on Indenter Modulus Method
• The Cause Multiplicity and the Multiple Cause Style of Adverse Events in Japanese Nuclear Power Plants
• Trend Analysis of Explosion Events at Overseas Nuclear Power Plants
• Recent Operation Status of Pressurized Water Reactors in the U.S.A. ―Investigation of the Cause of Their High Capacity Factor―
• Trend Analysis of Nuclear Reactor Automatic Trip Events at Nuclear Power Plants
• Comparison of Maintenance Workerʼs Human Error Events Occurred at United States and Domestic Nuclear Power Plants ―The Proposal of the Classification Method with Insufficient Knowledge and Experience and the Classification Result of Its Application―
• Analyses of the Trends in Motor Problems at Nuclear Power Plants in the United States
• Evaluation of the Contribution of License Renewal of Nuclear Power Plants to Fault Reduction in the U.S.
• Basic Study on a Technique for Predicting Break Diameter from Primary Cooling System in a Nuclear Emergency
• Main Steam Line Break Benchmark Analysis by Using The RELAP5-3D Code and Visualization of The Results.

Review

• Fifteen Yearsʼ Research Activities of the INSS Institute of Nuclear Technology and Future Policy

Document

• A Study of the Public Opinion concerning Nuclear Power Generation in the United States

Comments

• A company-wide activity to grow safety culture in a maintenance department of nuclear power plant
• The Research Project on Technical Information Basis for Aging Management in Fukui and Kinki Area
• Development of Detection Methods of Cavitation Phenomena by Sensor Placed outside of the Piping―Ten Years Summary of This Approach―