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하나로 핵연료시험설비의 냉각수상실사고 해석 방법의 보수성 고찰

원문정보

Consideration on the Conservatism of LOCA Analysis for the HANARO Fuel Test Loop

박수기, 박국남, 지대영, 안성호

피인용수 : 0(자료제공 : 네이버학술정보)

초록

영어

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. 서 론
 2. 핵연료시험설비의 설계 특성
 3. 해석 방법
  3. 1 전산 해석 프로그램
  3. 2 열수력 해석 모델링
  3. 3 배관 파단 모델링
 4. 결 과
  4. 1 임계유량 모델 고찰
  4. 2 물-금속 반응 모델 고찰
  4. 3 열전달 상관식 고찰
 5. 결 론
 참고문헌

저자정보

  • 박수기 S. K. PARK. 한국원자력연구소
  • 박국남 K. N. PARK. 한국원자력연구소
  • 지대영 D. Y. CHI. 한국원자력연구소
  • 안성호 S. H. AHN. 한국원자력연구소

참고문헌

자료제공 : 네이버학술정보

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