하나로 핵연료시험설비의 냉각수상실사고 해석 방법의 보수성 고찰 Consideration on the Conservatism of LOCA Analysis for the HANARO Fuel Test Loop
한국기계기술학회지
(韓國機械技術學會誌)
제9권 제2호
(2007.06)
pp.1-7
pp.1-7
한국기계기술학회
(Korean Society of Mechanical Technology)
초록
The conservative method on the analysis of loss-of-coolant accidents for the HANARO fuel test loop was established based on the guide of evaluation method for the emergency core cooling systems of pressurized light water reactors. The evaluation models, the Moody model for discharge rate calculation and the Baker-Just model for water-metal reaction calculation, were used. In order to calculate conservative peak cladding temperatures for accidents the multipliers to the correlations of heat transfer coefficients in the MARS were also introduced. Consequently it is found that the maximum peak cladding temperature predicted by using the conservative method is sufficiently greater than that calculated by using the best-estimated models.
목차
Abstract
1. 서론
2. 핵연료시험설비의 설계 특성
3. 해석 방법
3. 1 전산 해석 프로그램
3. 2 열수력 해석 모델링
3. 3 배관 파단 모델링
4. 결과
4. 1 임계유량 모델 고찰
4. 2 물-금속 반응 모델 고찰
4. 3 열전달 상관식 고찰
5. 결론
참고문헌
1. 서론
2. 핵연료시험설비의 설계 특성
3. 해석 방법
3. 1 전산 해석 프로그램
3. 2 열수력 해석 모델링
3. 3 배관 파단 모델링
4. 결과
4. 1 임계유량 모델 고찰
4. 2 물-금속 반응 모델 고찰
4. 3 열전달 상관식 고찰
5. 결론
참고문헌
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