The small break loss-of-coolant accidents for the HANARO fuel test loop have been predicted by MARS code. Conservative method was used for the prediction of the loss-of-coolant accidents. The maximum peak cladding temperature was calculated as 1286K, which was lower than the design limit temperature (1477K) of nuclear fuels for the HANARO fuel test loop. The maximum peak cladding temperature occurred for the cold leg break in the HANARO pool. The hydrogen generation and oxidation of the fuel cladding were also negligible. Consequently, it is ensured that the emergency cooling water system for the HANARO fuel test loop is appropriate for the small break loss-of-coolant accidents.

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 및 분석
  4.1 하나로 수조 안에서의 배관 파단 사고
  4.2 제1기기실에서의 배관 파단 사고
 5. 결론
 참고문헌

• 박수기(한국원자력연구원 연구로공학부) | S. K. PARK
• 지대영(한국원자력연구원 연구로공학부) | D. Y. CHI
• 안성호(한국원자력연구원 연구로공학부) | S. H. AHN