한국압력기기공학회 논문집 (Transactions of the Korean Society of Pressure Vessels and Piping)

한국압력기기공학회 (Korean Society of Pressure Vessels and Piping)
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재관수 실증실험과 TRACE 코드를 활용한 모델 변수의 불확실도 정량화

Uncertainty Quantification of Model Parameters Using Reflood Experiments and TRACE Code

  • Seon Oh Yu (Korea Institute of Nuclear Safety, Univ. of Science and Technology) ;
  • Kyung Won Lee (Korea Institute of Nuclear Safety)
  • 투고 : 2024.05.23
  • 심사 : 2024.06.19
  • 발행 : 2024.06.30
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초록

The best estimate plus uncertainty methodologies for loss-of-coolant accident analyses make use of the best-estimate codes and relevant experimental databases. Inherently, best-estimate codes have various uncertainties in the model parameters, which can be quantified by the dedicated experimental database. Therefore, this study was devoted to establishing procedures for identifying the input parameters of predictive models and quantifying their uncertainty ranges. The rod bundle heat transfer experiments were employed as a representative reflood separate effect test, and the TRACE code was utilized as a best-estimate code. In accordance with the present procedure for uncertainty quantification, the integrated list of the influential input parameters and their uncertainty ranges was obtained through local sensitivity calculations and screening criteria. The validity of the procedure was confirmed by applying it to uncertainty analyses, which checks whether the measured data are within computed ranges of the variables of interest. The uncertainty quantification procedure proposed in this study is anticipated to provide comprehensive guidance for the conduct of uncertainty analyses.

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과제정보

본 연구는 원자력안전위원회의 재원으로 한국원자력안전재단의 지원을 받아 수행한 원자력안전규제기술개발사업의 연구결과입니다(No. 2106002).

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