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Institute of Social Research Articles

A studyof viewpoints in making an effective counter-plan against an unusual event using factor analysis
A study on peopleʼs awareness of the causal factors of the Fukushima Dai-ichi accident and measures to ensure nuclear power plants safety ―Questionnaire survey conducted in the Kansai area―
The current state of radiation education in schools and results of the opinion survey on radiation

Institute of Nuclear Technology Articles

Effect of Pipe Shapes on Penetration Length in a Closed Straight Branch Pipe
An Investigation of Wall Temperature Characteristics to Improve Evaluation Method for Thermal Fatigue at a T-Junction Pipe
Investigation on Field Method Using Strain Measurement on Pipe Surface to Measure Pressure Pulsation in Piping Systems
A Proposed Simplified Design of Piping Systems Using Allowable Support Span Method ―Overhanging Technique and Allowable Support Span Based on Theoretical Solution―
Impact of Deformation Stiffness beyond the Yield Point of Steel Pipe Support Structures on SeismicResponse of Piping Systems
Development of the Method to Measure Vibrational Stress of Small-Bore Piping with Contactless Displacement Sensor ―Accuracy Confirmation by Vibrational Experiment Using Branch Pipe―
Effect of cold work on initiation stage crack growth rate of nickel based alloys
Atom Probe Tomography Characterizations of Medium-Cu Reactor Pressure Vessel Steels from a PWR Surveillance Test Program
Effects of helium on grain boundary fracture of neutron-irradiated stainless steel
Role of cavity formation in SCC of cold worked carbon steel in high-temperature water ―Part 1: Study of crack growth behavior―
Role of cavity formation in SCC of cold worked carbon steel in high-temperature water ―Part 2: Study of crack initiation behavior―
Damage Assessment of Low-cycle Fatigue by Crack Growth Prediction (Fatigue Life under Cyclic Thermal Stress)
Measurement of depth of SCC in Ni based alloy weldment by a Phased Array TOFD UT Method with asymmetrical ultrasonic beams(Ⅱ) ―Application to measurement on the crack side and the not crack side with nozzle shape―
An evaluation of detection ability of ultrasonic testing with a large aperture transducer for axial cracks in cast stainless steel pipe welds
Influence of Mean stress on Fatigue Strength of Stainless Steel
Transient evaluation using EMTP at one phase opening of the offsite power transformer of the emergency power supply systems for nuclear power plants
Development of a Rapid Prediction Technique for the Radioactivity Release Rate in Nuclear Emergency Preparedness ―Comparison Calculation of Radioactivity Release for BWR Plants―
Development and application of a radioactivity evaluation technique the to obtain radiation exposure dose of radioactivity evaluation technique when a severe accident occurs in the a power station of a severe accident 〜Accident management guidelines of knowledge-based maintenance〜
Application of the Best Estimate Plus Uncertainty (BEPU) method to the small break LOCA with high pressure injection failure: Integral effects test analysis
Application of the statistical safety evaluation method to the small break LOCA with high pressure injection failure 〜sensitivity analyses to determine the break conditions〜

Document

Safety-critical human factors issues derived from analysis of the TEPCO Fukushima Daiichi accident investigation reports

Review

A survey of lectures given at universities about energy and environmental issues 〜Seeking a viewpoint regarding energy and environmental education in junior and senior high schools〜

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