Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor-Reference-Cited by-同舟云学术

Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor

Published:2016-10 Issue:5 Volume:48 Page:1174-1183
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Dehjourian Mehdi,Sayareh Reza,Rahgoshay Mohammad,Jahanfarnia Gholamreza,Shirani Amir Saied

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference7 articles.

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2. MELCOR 1.8.6 Code Manuals,2005

3. U.S. EPR Severe Accident Evaluation Topical Report, 2006.

4. Nordostschweizerische Kraftwerke AG, Beznau (KKB), Safety Analysis Report, 2003.

5. OECD, Documentation of the Use of Severe Accident Computer Codes in Selected Level-2 PSAs for Nuclear Power Plants, Nuclear Energy Agency COMMITTEE on the Safety of Nuclear Installations, NEA/CSNI/R 19 (1998) 97.

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