Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel
Author:
Affiliation:
1. Nuclear Safety Research Center, Japan Atomic Energy Agency, 2-4 Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan
2. Research Institute of Nuclear Engineering, University of Fukui, 1-3-33 Kanawa-cho, Tsuruga-shi, Fukui 914-0055, Japan
Abstract
Publisher
ASME International
Subject
Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality
Link
http://asmedigitalcollection.asme.org/pressurevesseltech/article-pdf/doi/10.1115/1.4049048/6595931/pvt_143_03_031704.pdf
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4. Influence Evaluation of Loading Conditions During Pressurized Thermal Shock Transients Based on Thermal-Hydraulics and Structural Analyses;Front. Mech. Eng.,2018
5. Effect of Non-Uniform Reactor Cooling on Fracture and Constraint of a Reactor Pressure Vessel;Fatigue Fract. Eng. Mater. Struct.,2018
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