Paper Profile


Study of Neutronics and Thermal-hydraulics Coupling with RMC/COBRA-EN System


Documents: Full paper available in Conference Proceedings.
 
Date: Monday October 19
Time:15:25 - 15:50
 
Session:1B3: Monte Carlo I
 
Authors: Shichang Liu (Tsinghua University, China)
Jiankai Yu (Tsinghua University, China)
Jingang Liang (Tsinghua University, China)
Kan Wang (Tsinghua University, China)
Abstract:

Neutronics and Thermal-hydraulics (N-TH) coupling plays an important role in high fidelity multi-physics simulation for nuclear reactor analysis. A coupled N-TH code system based on a continuous-energy Monte Carlo code RMC and the sub-channel code COBRA-EN has been developed. The temperature dependence of nuclear cross sections is handled with the Fast Doppler Broadening (FDB) capability embedded in RMC. This code system has been applied to a PWR fuel pin and a fuel assembly to investigate the effects of N-TH coupling and Doppler broadening. The results show that the coupling system with Doppler broadening is effective for the thermal-hydraulics feedback.

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