Validation of the MELCOR input model for a CANDU PHWR containment analysis by benchmarking against integrated leakage rate tests-Reference-Cited by-同舟云学术

Validation of the MELCOR input model for a CANDU PHWR containment analysis by benchmarking against integrated leakage rate tests

Published:2018-12 Issue: Volume:340 Page:201-218
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kim Han-Chul,Pak Su-Kyoung,Lee Jun-Soo,Cho Song-Won

Funder

Korea Foundation of Nuclear Safety

Nuclear Safety and Security Commission

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference17 articles.

1. American Nuclear Society, 2002. Containment System Leakage Testing Requirements, ANSI/ANS-56.8-2002.

2. Candu Energy Inc. (formerly AECL), 1995. Analysis Report: Containment models, 86-03500-AR-006, Rev.2.

3. MELCOR Simulations of the Severe Accident at the Fukushima 1F3 Reactor;Cardoni,2012

4. MELCOR simulations of the severe accident at the Fukushima Daiichi Unit 1 reactor;Gauntt;Nucl. Technol.,2014

5. MELCOR Computer Code Manuals;Guantt,2005

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