The comparison of designed water-cooled and air-cooled passive residual heat removal system for 300MW nuclear power plant during the feed-water line break scenario

Author:

Wang Mingjun,Qiu Suizheng,Tian Wenxi,Su Guanghui,Zhang Yapei

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference12 articles.

1. Design, experiments and RELAP5 code calculations for the PERSEO facility;Ferri;Nucl. Eng. Des.,2005

2. IAEA activities on passive safety systems and overview of international development;Juhn;Nucl. Eng. Des.,2000

3. AP1000 passive core cooling system pre-operational tests procedure definition and simulation by means of RELAP5 Mod. 3.3 computer code;Lioce;Nucl. Eng. Des.,2012

4. Munther, R., 1996. Gravity driven emergency core cooling experiments with the PACTEL facility. In: Proceedings of an Advisory Group Meeting, 357, pp. 219–230.

5. RELAP5/MOD3.3, 2001. Code Manual Volume 1: Code Structure, System Models, and Solution Methods NUREG/CR-5535.

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