Development and verification of core physical-thermal coupling code based on unified coupling framework
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1.School of Nuclear Science and Technology, University of Science Technology of China;2.Nuclear Power Institute of China

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TL325

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    Abstract:

    In order to realize the comprehensive simulation of the multi-physics and multi-scale field of the reactor, based on the unified coupling interface concept Interface for Code Coupling (ICoCo) and the unified data transfer model MED library, the space-time neutronics simulation code CORCA-K and the sub-channel code CORTH have been packaged. Furthermore, the coupling between CORCA-K and CORTH was realized by using the supervisor method. The code was verified by the rod ejection cases of 3D LWR core transient benchmark NEACRP. The numerical results show that the CORCA-K and CORTH coupling code based on the unified coupling framework can realize the field data transfer and coupling calculation between CORCA-K and CORTH. The calculation results are in good agreement with those of the CORCA-K coupling interface, and the two results are basically consistent with the benchmark ones.

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Cite this article as: JIANG Rong, FENG Wen-Pei, CHEN Hong-Li, QIANG Sheng-Long, LI Zhi-Gang, PAN Jun-Jie, ZHANG Xi-Lin, LUO Xiao. Development and verification of core physical-thermal coupling code based on unified coupling framework [J]. J Sichuan Univ: Nat Sci Ed, 2021, 58: 044006.

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History
  • Received:December 05,2020
  • Revised:January 10,2021
  • Adopted:January 21,2021
  • Online: July 12,2021
  • Published: