10:30 AM - 10:45 AM
[3K05] Estimation of RPV damage and fuel debris relocation behavior in the PCV at Fukushima Daiichi Nuclear Power Station
(5)Evaluation of temperature behavior of CRD Housing of Unit 2 during accident progress
Keywords:Fukushima Daiichi Nuclear Power Station, Severe accident, Accident analysis
In this case, the pressure vessel damage behavior of Unit 2 (1F2) of Fukushima Daiichi Nuclear Power Plant is evaluated as a part of the series of presentations "Estimation of RPV damage and fuel debris relocation behavior in the PCV at Fukushima Daiichi Nuclear Power Station".
In this presentation, the temperature behavior of the CRD housing in the RPV boundary during accident progression is reported by thermal-hydraulic analysis using Ansys Fluent.
In this presentation, the temperature behavior of the CRD housing in the RPV boundary during accident progression is reported by thermal-hydraulic analysis using Ansys Fluent.
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