지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 1,174 - 1,183 (10page)
이용수
초록· 키워드
오류제보하기
Hydrogen release during severe accidents poses a serious threat to containment integrity.
Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of overpressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steamand the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity. The MELCOR 1.8.6 was used to assess core degradation and containment behavior during the large break loss-of-coolant accident without the actuation of the safety injection system except for accumulators in Beznau nuclear power plant. Also, hydrogen distribution in containment and performance of hydrogen reduction system were investigated.
목차
등록된 정보가 없습니다.
참고문헌 (7)
참고문헌 신청
2011 / Mitigation of Hydrogen Hazards in Severe Accidents in Nuclear Power Plants, IAEA-TECDOC-1661 / International Atomic Energy Agency
MELCOR 1.8.6 Code Manuals / 2005 / Primer and Users' Guide Version 1.8.6, vol. 1
2006 / U.S. EPR Severe Accident Evaluation Topical Report
Nordostschweizerische Kraftwerke AG / 2003 / Safety Analysis Report
OECD / 1998 / Documentation of the Use of Severe Accident Computer Codes in Selected Level-2 PSAs for Nuclear Power Plants :97
MELCOR 1.8.6 Code Manuals / 2005 / Primer and Users' Guide Version 1.8.6, vol. 1
2006 / U.S. EPR Severe Accident Evaluation Topical Report
Nordostschweizerische Kraftwerke AG / 2003 / Safety Analysis Report
OECD / 1998 / Documentation of the Use of Severe Accident Computer Codes in Selected Level-2 PSAs for Nuclear Power Plants :97
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