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A Safety Analysis of a Steam Generator Module Pipe Break for the SMART-P  

Kim Hee Kyung (Korea Atomic Energy Research Institute)
Chung Young-Jong (Korea Atomic Energy Research Institute)
Yang Soo-Hyung (Korea Atomic Energy Research Institute)
Kim Hee-Cheol (Korea Atomic Energy Research Institute)
Zee Sung-Quun (Korea Atomic Energy Research Institute)
Publication Information
International Journal of Safety / v.3, no.1, 2004 , pp. 53-58 More about this Journal
Abstract
SMART-P is a promising advanced small and medium category nuclear power reactor. It is an integral type reactor with a sensible mixture of new innovative design features and proven technologies aimed at achieving a highly enhanced safety and improved economics. The enhancement of the safety and reliability is realized by incorporating inherent safety improving features and reliable passive safety systems. The improvement in the economics is achieved through a system simplification, and component modularization. Preliminary safety analyses on selected limiting accidents confirm that the inherent safety improving design characteristics and the safety system of SMART-P ensure the reactor's safety. SMART-P is an advanced integral pressurized water reactor. The purpose of this study is for the safety analysis of the steam generator module pipe break for the SMART-P. The integrity of the fuel rod is the major criteria of this analysis. As a result of this analysis, the safety of the RCS and the secondary system is guaranteed against the module pipe break of a steam generator of the SMART-P.
Keywords
SMART-P; integral reactor; safety analysis; module pipe break;
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  • Reference
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