Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in Nuclear Power Plants-Reference-Cited by-同舟云学术

Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in Nuclear Power Plants

Published:2020-01 Issue: Volume:118 Page:103105
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Cheng Wen-Chi,Sakurahara Tatsuya,Zhang Sai^ORCID,Farshadmanesh Pegah,Reihani Seyed,Kee Ernie,Mohaghegh Zahra^ORCID,Heckmann Klaus,Sievers Jürgen^ORCID,Lydell Bengt,Zammali Chokri,Yuan Xian-Xun,Duan Xinjian,Alzbutas Robertas,Lee Gyeong-Geun,Karim Julia Abdul,Morozov Vladimir,Takasugi Cole,Jevremovic Tatjana

Funder

Office of Science

Nuclear Energy University Program

International Atomic Energy Agency

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference291 articles.

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