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하나로 핵연료시험설비의 대형냉각수상실 사고 시 핵연료 피복재 Prediction on the Nuclear Fuel Cladding Temperatures for the LBLOCAs of the HANARO Fuel Test Loop

박수기, 지대영, 박국남, 안성호
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한국기계기술학회지 (韓國機械技術學會誌)
제9권 제3호 (2007.09)
pp.53-58
한국기계기술학회 (Korean Society of Mechanical Technology)
초록

The nuclear fuel cladding temperatures of the HANARO fuel test loop have been calculated by MARS code for the large break loss-of-coolant accidents. Conservative method was used for the analysis of the loss-of-coolant accidents. Consequently, the maximum peak cladding temperature was predicted as 1235K, which was lower than the design limit temperature (1477K) of nuclear fuels for the HANARO fuel test loop. This means that the cooling capability of the emergency cooling water system for the HANARO fuel test loop is sufficient for the large break loss-of-coolant accidents.

키워드
HANARO하나로Fuel Test Loop핵연료시험설비LBLOCA대형냉각수상실 사고
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 하나로 수조 안 배관의 양단파단 사고
  4. 2 제1기기실 배관의 양단파단 사고
 5. 결론
 참고문헌
저자
  • 박수기(한국원자력연구원) | S. K. PARK
  • 지대영(한국원자력연구원) | D. Y. CHI
  • 박국남(한국원자력연구원) | K. N. PARK
  • 안성호(한국원자력연구원) | S. H. AHN