Off-site consequence analyses of ISLOCA & MSGTR severe accidents in CANDU-6 plants using the WinMACCS code-Reference-Cited by-同舟云学术

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Off-site consequence analyses of ISLOCA & MSGTR severe accidents in CANDU-6 plants using the WinMACCS code

Published:2021-02 Issue: Volume:372 Page:110980
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lim Chul-Kyu,Jin Dong-Sik,Kim Sung-yeop,Ahn Kwang-Il,Han Sang-Koo,Kim Sook-Kwan,Ko Bong-Jin,Hong Yong-Ho,Hwang Seok-Won

Funder

Korea Atomic Energy Research Institute

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

Reference23 articles.

1. U.S.NRC, 2012. State-Of-the-Art Reactor Consequence Analyses Report, NUREG-1935.

2. Kwang-Il Ahn, Seok-Won Hwang, 2017. The KHNP SOARCA Project: Development Strategy, KHNP Severe Accident and SOARCA Workshop, Sandia National Laboratories, Albuquerque, NM, April 17.

3. KAERI, 2008. ISAAC Code User's Manual, KAERI Technical Report KAERI/TR-3645.

4. U.S.NRC, 2017. MACCS User’s Guide and Reference Manual, NUREG/CR-XXXX, Draft Report.

5. U.S.NRC, 2014. MACCS Best Practices as Applied in the State-of-the-Art Reactor Consequence Analyses (SOARCA) Project, NUREG/CR-7009.

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