A PRELIMINARY EVALUATION OF UNPROTECTED LOSS-OF-FLOW ACCIDENT FOR A PROTOTYPE FAST-BREEDER REACTOR

TOHRU SUZUKI; Yoshiharu Tobita; KENICHI KAWADA; HIROTAKA TAGAMI; JOJI SOGABE; KENICHI MATSUBA; KEI ITO; HIROYUKI OHSHIMA

추천

검색

자료유형: 학술저널

저자정보: TOHRU SUZUKI (Japan Atomic Energy Agency) Yoshiharu Tobita (Japan Atomic Energy Agency) KENICHI KAWADA (Japan Atomic Energy Agency) HIROTAKA TAGAMI (Japan Atomic Energy Agency) JOJI SOGABE (Japan Atomic Energy Agency) KENICHI MATSUBA (Japan Atomic Energy Agency) KEI ITO (Japan Atomic Energy Agency) HIROYUKI OHSHIMA (Japan Atomic Energy Agency)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제47권 제3호

발행연도: 2015.4

수록면: 240 - 252 (13page)

이용수

📌

연구주제

📖

연구배경

🔬

연구방법

🏆

연구결과

초록· 키워드

오류제보하기

In the original licensing application for the prototype fast-breeder reactor, MONJU, the event progression during an unprotected loss of flow (ULOF), which is one of the technically inconceivable events postulated beyond design basis, was evaluated. Through this evaluation, it was confirmed that radiological consequences could be suitably limited even if mechanical energy was released. Following the Fukushima-Daiichi accident, a new nuclear safety regulation has become effective in Japan. The conformity of MONJU to this new regulation should hence be investigated. The objectives of the present study are to conduct a preliminary evaluation of ULOF for MONJU, reflecting the knowledge obtained after the original licensing application through CABRI experiments and EAGLE projects, and to gain the prospect of in-vessel retention for the conformity of MONJU to the new regulation. The preliminary evaluation in the present study showed that no significant mechanical energy release would take place, and that thermal failure of the reactor vessel could be avoided by the stable cooling of disrupted-core materials. This result suggests that the prospect of in-vessel retention against ULOF, which lies within the bounds of the original licensing evaluation and conforms to the new nuclear safety regulation, will be gained.

#Core disruptive accident (CDA) #In-vessel retention (IVR) #Sodium-cooled fast reactor (SFR) #Unprotected loss of flow (ULOF) #SAS4A #SIMMER-III/IV

참고문헌 (21)

참고문헌 신청

Japan Atomic Energy Agency / 1980 / The Licensing Document for the Construction Permit of the Prototype FBR Monju

Nuclear Regulation Authority

Japan Atomic Energy Agency / Improvement of Accident Management for the Prototype FBR Monju

G. Kussmaul / 1986 / The CABRI Project d Overall Status and Achievements / Proceedings of Science and Technology of Fast Reactor Safety :103

M. Haessler / 1990 / The CABRI-2 Programme d Overview on Results / Proceedings of the International Fast Reactor Safety Meeting 2:209

함께 읽어보면 좋을 논문

논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!