Verification of a HC-PK-CFD coupled program based a benchmark on beam trip transients for XADS reactor

Author:

Gu Zhixing,Li Fei,Ge Liangquan,Zeng Guoqiang,Zhang Qingxian,Shi Jialei

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference23 articles.

1. Asaka, H., Zimin, V.G., Iguchi, T., et al. 2001. Coupling of the thermal-hydraulics TRAC codes with 3-D neutron kinetics code SKETCH-N[R].

2. A coupled RELAP5-3D/CFD methodology with a proof-of-principle calculation;Aumiller;Nucl. Eng. Design,2001

3. A first system/CFD coupled simulation of a complete nuclear reactor transient using CATHARE2 and TRIO_U. Preliminary validation on the Phénix Reactor Natural Circulation Test;Baviere;Nucl. Eng. Design,2014

4. TMI-1 MSLB coupled 3-D neutronics/thermal hydraulics analysis: application of RELAP5-3D and comparison with different codes;Bovalini;Dokladi na BYaD,2003

5. Coupling a CFD code with neutron kinetics and pin thermal models for nuclear reactor safety analyses;Chen;Ann. Nucl. Energy,2015

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