Analysis of severe accident progression and Cs behavior for SBO event during mid-loop operation of OPR1000 using MELCOR-Reference-Cited by-同舟云学术

Analysis of severe accident progression and Cs behavior for SBO event during mid-loop operation of OPR1000 using MELCOR

Published:2021-09 Issue:9 Volume:53 Page:2859-2865
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Park Yerim^ORCID,Shin Hoyoung,Kim Seungwoo^ORCID,Jin Youngho,Kim Dong Ha,Jae Moosung

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference18 articles.

1. Nuclear Power Reactors in the World 2019 Edition,2019

2. LPSD Internal Events Level 1 PSA Report for Shin-Kori Units 1&2;Hydro,2015

3. U.S. Nuclear Regulatory Commission, Loss of Residual Heat Removal System: Diablo Canyon, Unit 2, April 10, 1987, NUREG-1269.

4. U.S. Nuclear Regulatory Commission, Loss of Vital AC Power and the Residual Heat Removal System during Mid-loop Operations at Vogtle Unit 1 on March 20, 1990, NUREG-1410.

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