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Preliminary safety evaluation for CSR1000 with passive safety system
Annals of Nuclear Energy, 2014Abstract This paper describes the preliminary safety analysis of the Chinese Supercritical water cooled Reactor (CSR1000), which is proposed by Nuclear Power Institute of China (NPIC). The two-pass core design applied to CSR1000 decreases the fuel cladding temperature and flattens the power distribution of the core at normal operation condition. Each
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Variations of a passive safety containment for a BWR with active and passive safety systems
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