Probabilistic safety impacts of advanced design features in Korean next generation reactor
- Korea Electric Power Research Institute, Taejon (Korea, Republic of)
Center for Advanced Reactor Development (CARD) of Korea Electric Power Research Institute (KEPRI) has been currently developing Korean Next Generation Reactor (KNGR). It incorporates several active and passive advanced design features (ADFs) to increase the plant safety compared to that of existing plant or previously designed advanced light water reactors (ALWRs). To see the effects of these safety features, design specific probabilistic safety assessment (PSA) is considered. It is a basic policy to perform level III full scope PSA whose goal is to satisfy the ultimate safety clarified in severe accident implementation rule. This paper reports the preliminaries (or the first evaluation) of our effort into safety aspects, especially, into the design validity of some ADFs, focused on the passive secondary condensing system (PSCS) in KNGR, to reinforce the existing safety systems in the point of PSA. 6 refs., 2 figs., 5 tabs.
- Research Organization:
- American Nuclear Society, La Grange Park, IL (United States)
- OSTI ID:
- 552121
- Report Number(s):
- CONF-970607--Vol.2
- Country of Publication:
- United States
- Language:
- English
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