Institute of Nuclear Technology

Yoshio Shimada

Research Articles

201623088095	The Development and Utilization of Quantitative Assessment Method with regard to the Operating Experience Information Analyses of Nuclear Power Plants
201522153164	Transient evaluation using EMTP at one phase opening with the off site power transformer for the emergency power supply systems of nuclear power plants （This report is a follow-up of the report published two years ago.） －Verifi cation related to the open-phase detection method of the transformer by United States Electric Power Research Institute（EPRI）－
201421185195	Transient evaluation using EMTP at one phase opening of the off site power transformer of the emergency power supply systems for nuclear power plants （This report is a follow-up the last year’s.）
201320204223	Transient evaluation using EMTP at one phase opening of the offsite power transformer of the emergency power supply systems for nuclear power plants
201219221237	Evaluating the Transient Performance of Emergency Diesel Generators by Computer Simulation
201118267274	Trend Analyses of the Emergency Diesel Generator Problem Events in Japanese and U.S. Nuclear Power Plants
201017231246	Investigation of Practical Use Situation and Performance for Electric Transient Analysis Programs in the U.S. Nuclear Power Plants
200916228232	Trend Analyses of Transformer Problems in the U.S. Nuclear Power Plants
200815287294	Analyses of the Trends in Motor Problems at Nuclear Power Plants in the United States
200714316325	Comparison between Japan and the United States in the Frequency of Events in Equipment and Components at Nuclear Power Plants
200613281285	Events Analysis of the Main Generator Using Reliability Block Diagram
200512118127	Method of Extracting Significant Trouble Information of Nuclear Power Plants using Probabilistic Analysis Technique
200411087094	A Probabilistic Safety Assessment Approach toward Identification of Information on Safety Significant Adverse Events at Overseas Nuclear Power Plants
200310093098	Database Construction Using Hyperlink of Reliability Block Diagram and Operating Experiences of Emergency Diesel Generators for Nuclear Power Plants
200209058066	Analysis of Convergence of Uncertainty and Important Factors Affecting Uncertainty in Level 1 PSA for Pressurized Water Reactors
200108071079	Development of a New Model to Evaluate the Probability of Automatic Plant Trips for Pressurized Water Reactors
200007239243	Evaluation of Nuclear Power Plant Component Failure Probability and Core Damage Probability using Simplified PSA Model