Round robin analysis of vessel failure probabilities for PTS events in Korea-Reference-Cited by-同舟云学术

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Round robin analysis of vessel failure probabilities for PTS events in Korea

Published:2020-08 Issue:8 Volume:52 Page:1871-1880
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Jhung Myung Jo,Oh Chang-Sik,Choi Youngin,Kang Sung-Sik,Kim Maan-Won,Kim Tae-Hyeon,Kim Jong-Min,Kim Min Chul,Lee Bong Sang,Kim Jong-Min,Kim Kyuwan

Funder

Korea Foundation of Nuclear Safet

Nuclear Safety and Security Commission(NSSC) of the Republic of Korea

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference13 articles.

1. Probabilistic fracture mechanics round robin analysis on reactor pressure vessels during pressurized thermal shock;Jhung;J. Nucl. Sci. Technol.,2010

2. Comparison Report of RPV Pressurized Thermal Shock International Comparative Assessment Study (PTS ICAS), NEA/CSNI/R(99)3;OECD/NEA,1999

3. Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment, IAEA-TECDOC-1627;IAEA,2010

4. PFM Round Robin Analysis on RPV Integrity During PTS by Korean Participants, KINS/RR-686;KINS,2009

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Evaluation of Probabilistic Fracture Mechanics for Reactor Vessel Using FAVOR Code;Transactions of the Korean Society of Mechanical Engineers - A;2022-07-31

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