engleski

Analysis of International Standard Problem ISP-45 on QUENCH Facility Using RELAP5/SCDAPSIM/MOD3.2 Computer Code

This paper presents the analysis of OECD/NEA International Standard Problem no. 45 (ISP-45) that was performed as experiment QUENCH-06 in Forschungszentrum Karlsruhe (FZK). The objective of the experiment was the investigation of the core behaviour during a severe accident (particularly fuel rod claddings behaviour and the hydrogen release when the overheated nuclear reactor core is flooded as a part of an accident management measure), while the objective of the ISP is code validation, i.e., reliability and accuracy of severe accidents codes, especially during quench (reflood) phase. For the purpose of modelling the QUENCH facility and ISP-45 calculation RELAP5/SCDAPSIM MOD3.2(bht) computer code was used. The analysis was performed in two different phases. The first phase was a blind calculation of the whole test on the basis of general data of the facility, like geometry, and of the specific experimental initial and boundary conditions. The open calculation based on the experimental results of QUENCH-06 was the second step in the analysis. This paper covers the open calculation

Nuclear power plant; quench experiment; severe accidents

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