Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1998.05a
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- Pages.862-868
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- 1998
Insights from the KNGR Preliminary Level 1 Probabilistic Safety Assessment
- Na, Jang-Hwan (Korea Electronic Power Research Institute) ;
- Oh, Hae-Cheol (Korea Electronic Power Research Institute) ;
- Oh, Seung-Jong (Korea Electronic Power Research Institute)
- Published : 1998.05.01
Abstract
Korean Next Generation Reactor(KNGR) is a standardized evolutionary Advanced Light Water Reactor design under development Korea Power Company(KEPCO). It incorporates design enhncements such as active and passive advanced design features(ADFs) to increase the plant safety. A Preliminary level 1 Probabilistic Safety Assessment(PSA) has been performed for KNGR to examine the effect of these safety features. The preliminary PSA result shows that it meets the KNGR safety goal on core damage frequency(CDF). The result of this safety assessment shows that the four-train safety systems, and the ADFs such as Passive Secondary Cooling System (PSCS) contributes greatly to the reduction the CDF. Furthermore, several design changes are made or proposed for detailed review based on the PSA insights.
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