Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
6761789 | Nuclear Engineering and Design | 2015 | 13 Pages |
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 â2 to â4 °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.
Related Topics
Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
W.P. Chang, Y. Jin, C.W. Choi, K.S. Ha,