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Institute of Social Research Articles

Questionnaire survey on factors of unsafe driving behaviors at work
Change in perception towards radiation of people after being presented with a science-based description about it
Trend of public awareness and communication strategy to inform the public about radiation

Institute of Nuclear Technology Articles

Load carrying capacity assessment of cracked components by elastic-plastic fi nite element analysis （Investigation of load carrying capacity assessment procedures for stainless steel plates and pipes）
Eff ects of Local Flow Field on Flow Accelerated Corrosion – Wall Thinning Rate at an Elbow Pipe and Combination Eff ect of an Upstream Orifi ce –
Flow Structure in a Downward Branch Pipe with a Closed End （Characteristics of Flow Velocity in the Branch Pipe）
Study on PWSCC initiation condition on cold worked Alloy 690 using SSRT
Solute Cluster Formation in Austenitic Stainless Steel under Neutron Irradiation
Grain boundary oxidation of 3 dpa neutron-irradiated stainless steels in high temperature water
The Development and Utilization of Quantitative Assessment Method with regard to the Operating Experience Information Analyses of Nuclear Power Plants
Trend Analysis of Spring-loaded safety-relief valve Failure Events at U.S.Nuclear Plants
Study on Dose Calculation Method for Operational Intervention Level – Preparation of Calculation Expression and Dose Conversion Factors –
Analysis and Evaluation for ATWS Event by RELAP5（Mod.3.2）
Improvement of the severe accident practice tool

Review

Infl uence of long-term thermal aging on SCC Behavior of Cast Stainless Steels and stainless steel weld metals in High-Temperature Water – Current research status and Future Program –

Document

Learning Non-Technical Skill Lessons from Testimony Given in the Investigation of the Nuclear Accident at the Fukushima Nuclear Power Stations
Evaluation of the indenter modulus（IM）method in the international round robin test about the cable condition monitoring.

Comments

Integrity Assessment Method for Structural Materials of Nuclear Reactor after Suff ering an Earthquake – An Evaluation Method for Plastic Deformation by Measuring Hardness of the materials –

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