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Reactor Core Coolability Analysis during Hypothesized Severe Accidents of OPR1000
- Lee, Yongjae;
- Seo, Seungwon;
- Kim, Sung Joong;
- Ha, Kwang Soon;
- Kim, Hwan-Yeol
키워드
BWR TYPE REACTORS; COMPUTERIZED SIMULATION; COOLANTS; DESIGN; M CODES; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR OPERATION; SAFETY
- 제목
- Reactor Core Coolability Analysis during Hypothesized Severe Accidents of OPR1000
- 저자
- Lee, Yongjae; Seo, Seungwon; Kim, Sung Joong; Ha, Kwang Soon; Kim, Hwan-Yeol
- 발행일
- 2014-10
- 유형
- Proceeding
- 저널명
- 2014 Transactions of the Korean Nuclear Society Autumn Meeting
- 페이지
- 1 ~ 4