Conference Proceedings Paper
Benchmark Analyses of Sodium Convection in Upper Plenum of the MONJU Reactor Vessel - Comparison Between Plant System Analysis Code CERES and CFD Code
NURETH-14 - 2011 September 25-30
Yoshihisa Nishi (CRIEPI)
Nobuyuki Ueda (CRIEPI)
Shinji Yoshikawa (Japan Atomic Energy Agency)
Akira Miyakawa (Japan Atomic Energy Agency)
Mitsuya Kato (Japan Atomic Energy Agency)
In the CRP of IAEA, the data of the upper plenum geometry of the prototype FBR“MONJU” and the boundary conditions of the plant trip test were provided by JAEA. A plant system analysis code CERES for FBRs was developed by CRIEPI. To verify the CERES code, analyses had been performed for the system test of the MONJU, the results of which showed good agreement with the test. However, the difficulty of accurately reproducing the temperature variation arising from a complex flow in the upper plenum was identified. By using the general-purpose analysis code STAR-CCM+, detailed analysis in the upper plenum was enabled. Based on comparison between analyses of the CERES and STAR-CCM+ codes, parameters that had to be considered to simulate the flow pattern appropriately for plant system analysis codes were discussed. And, the analysis capability of CERES code with appropriate parameter was able to be confirmed.
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