Article ID Journal Published Year Pages File Type
6761789 Nuclear Engineering and Design 2015 13 Pages PDF
Abstract
As a result, most of the comparative results between the MATRA-LMR-FB predictions and the test data lay within a range of ±15 °C. Such differences were not usually derailed much from other predictions found in a literature survey. The code, however, is slightly biased toward an under-prediction, with the most probable difference occurring at around −2 to −4 °C. Nevertheless, it was anticipated that the comparison will supplement the applicability of the MATRA-LMR-FB to a partial flow blockage accident in a subassembly of an SFR. The CFX simulation results mostly agreed with the MATRA-LMR-FB predictions.
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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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