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Application of REFLA Core Model to Safety Evaluation Code
Abstract:In the analysis of the core thermal-hydraulic behavior during the reflood phase of a PWR-LOCA, current safety evaluation codes like WREM code system are usually limited to use in narrow region where the employed empirical correlations are validated. In order to make a safety evaluation code more flexibly applicable, the empirical correlations in TOODEE2 code in the WREM code system was replaced with the core model built in the REFLA code. By changing the multiplication factor for the calculated heat transfer coefficient for the region above the quench front, the predicted clad surface temperatures were compared with those measured in Cylindrical Core Test Facility (CCTF) tests.

It was found that the multiplication factor 0.9 gives always a conservative prediction against CCTF data.
Keywords:reactor safety  PWR type reactors  loss of coolant  reflood  thermohydraulics  heat transfer  safety evaluation analysis  WREM code system  REFLA core model  empirical correlation  CCTF tests  computer codes
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