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Institute of Social Research Articles

Peopleʼs response to the promotion of the effective use of nuclear power plants ―From the viewpoint of favoring providing information about maintenance activities―
A study on the effect of context on peopleʼs perception of a small radiation leak at a nuclear power plant
Social Acceptance for Seismic Safety of Nuclear Installations
Factors Constituting Trust in Public Utilities ―Comparison between Public Utilities and Private Companies―
The Development of Teaching Materials for Energy and Environmental Education Integrated into Main Subjects in Schools

Institute of Nuclear Technology Articles

Fast Computable Residual Stress Analysis for Welded Pipe Joint Based on Iterative Substructure Method
Investigation of Wall Temperature Fluctuations by Visualization Tests and Numerical Simulation for Steam-Water Two-phase flow in the Pressurizer Spray Piping
LDV measurements and URANS calculations downstream of a globe valve
Effects of Local Flow Field on Flow Accelerated Corrosion ―Effect of Flow Velocity on Corrosion Rate―
Development of Method to Measure Vibrational Stress of Small-Bore Piping with Multiple Contactless Displacement Sensors ―Vibration Test to Apply the Proposed Method to Practical Use―
Effect of Dissolved Hydrogen Concentration on PWSCC Crack Growth Rate of Alloy 600 at 290℃
Mechanistic Study on SCC Propagation of Welded Nickel Based Alloy, (V) ―Corrosion Behavior under Deaerated High-Temperature Water―
SCC growth behavior of stainless steel weld heat-affected zone in hydrogenated high temperature water
Damage due to Low-cycle Fatigue of Type 316 Stainless Steel ―Fatigue Life under Variable Loading and Influence of Internal Cracks―
Development ofmicro tensile testing method in an FIB system for evaluating grain boundary strength
Effects of hydrogen on interaction between dislocation and radiation-induced defects
FIB sequential sectioning as a tool to understand environmental materials degradation in 3D
A Study ofNon Destructive Integrity Assessment Method for Structural Materials ofNuclear Reactor -Part 1-
A Proposal for a Determination Method of Element Division on an Analytical Model for Finite Element Elastic Waves Propagation Analysis
Research and Analysis of On-line Maintenance Process and Problems at United States Nuclear Power Plants
Investigation of Practical Use Situation and Performance for Electric Transient Analysis Programs in the U.S. Nuclear Power Plants
Trend Analysis of Troubles Caused by Thermal-Hydraulic Phenomena at Nuclear Power Plants
Feasibility Study of Computerized Presentation of Procedures of a Nuclear Plant
Trend Analysis of the Adverse Event Cause in Nuclear power plants
Study on Examples of Safety Culture Enhancing Activities at U.S. Nuclear Power Stations
Main Steam Line Break Accident Analysis for 4-Loop PWR Plant by RELAP5-3D Code
Plant Incident Progress Scenario Analysis for Nuclear Emergency Exercise of Fukui Pref. 2009

Comments

The Research Project on Technical Information Basis for Aging Management in Fukui and Kinki Area (3rd Report)
Study on Counter-Current Flow in a PWR Hot Leg under Reflux Condensation
A concern about the crack propagation rate of PWSCC which obtained from the investigation on primary coolant leakage portion of the reactor vessel head in Ohi 3

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