CUPID 코드 기반 수소거동 해석 모델 방법론 연구

Abstract

In the wake of Fukushima accident, controlling the hydrogen risk has become a priority for the safety of nuclear power plants. While lumped-parameter system codes are computationally efficient, they do not provide precise information on the local hydrogen distribution. On the other hand, computational fluid dynamics (CFD) codes provide detailed information on local phenomena. In this work, a three-dimensional CFD simulation of the PANDA facility is developed using the CFD code, CUPID. Specifically, the simulation of the thermal-hydraulic experiments OECD/SETH-2 ST1 test series is presented in the current paper. The code predictions of the concentration during the mixing and stratification phases are compared to the experimental data. This effort is part of an ongoing effort to understand the local behavior of steam-hydrogen releases in nuclear reactor containment in support of accident management and simultaneously serves as a validation of the CUPID code to assess it applicability for containment analyses.