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Report No.
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Development of reactor vessel thermal-hydraulic analysis method in natural circulation conditions with coarse-mesh subchannel CFD model

Hamase, Erina ; Miyake, Yasuhiro*; Imai, Yasutomo*; Doda, Norihiro ; Ono, Ayako ; Tanaka, Masaaki  

To enhance the safety of sodium-cooled fast reactors, the natural circulation (NC) decay heat removal systems with a dipped-type direct heat exchanger (D-DHX) have been investigated. During the D-DHX operation, since the core-plenum interaction occurs, development of the reactor vessel model including the more model by using a computational fluid dynamics code (RV-CFD) is required. Previously, the CFD model based on the subchannel analysis was developed. In this study, to achieve much lower computational cost maintaining the prediction accuracy, the coarse-mesh subchannel CFD (CMSC) model has been developed and was incorporated into the core of RV-CFD. As a result of PLANDTL-1 test analysis, the RV-CFD with the CMSC model can reproduce the radial heat transfer under NC conditions.

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