Improvement in Neutron Transport of KYCORE Code

Tang Xiao; LI Qing; Chai Xiaoming; Tu Xiaolan; Wang Kan

doi:10.13832/j.jnpe.2017.S2.0011

Volume 38 Issue S2

Feb. 2025

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Tang Xiao, LI Qing, Chai Xiaoming, Tu Xiaolan, Wang Kan. Improvement in Neutron Transport of KYCORE Code[J]. Nuclear Power Engineering, 2017, 38(S2): 11-15. doi: 10.13832/j.jnpe.2017.S2.0011

Citation:

Tang Xiao, LI Qing, Chai Xiaoming, Tu Xiaolan, Wang Kan. Improvement in Neutron Transport of KYCORE Code[J]. Nuclear Power Engineering, 2017, 38(S2): 11-15. doi: 10.13832/j.jnpe.2017.S2.0011

Tang Xiao, LI Qing, Chai Xiaoming, Tu Xiaolan, Wang Kan. Improvement in Neutron Transport of KYCORE Code[J]. Nuclear Power Engineering, 2017, 38(S2): 11-15. doi: 10.13832/j.jnpe.2017.S2.0011

Citation:

Tang Xiao, LI Qing, Chai Xiaoming, Tu Xiaolan, Wang Kan. Improvement in Neutron Transport of KYCORE Code[J]. Nuclear Power Engineering, 2017, 38(S2): 11-15. doi: 10.13832/j.jnpe.2017.S2.0011

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Improvement in Neutron Transport of KYCORE Code

doi: 10.13832/j.jnpe.2017.S2.0011

1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China;
2. Tsinghua University, Beijing, 100084, China

Received Date: 2017-10-14
Rev Recd Date: 2017-12-04

Abstract

Abstract

KYCORE is a 3 D nuclear reactor numerical calculation software and it is developed from KYLIN-2, a 2 D assembly calculation software developed in Nuclear Power Institute of China. The neutron transport part uses 2 D MOC and 1 D SN coupling to realize high precision through direct angular flux coupling and is accelerated with coarse mesh finite difference（CMFD）. Due to the simplification in the calculation procedure, the KYCORE code may detergency in calculation, thus it is improved in calculation method and mesh dividing. The salability and accuracy of the KYCORE 3 D neutron transport calculation are verified with the comparison to Monte Carlo code and C5 G7 extension case.
- KYCORE,
- Neutron transport,
- MOC/SN coupling,
- CMFD