Development of Self-reliant Subchannel Analysis Code CORTH

Liu Yu; Tan Zhanglu; Pan Junjie; Wang Xiaoyu; Xu Liangjian; Deng Jian

doi:10.13832/j.jnpe.2017.06.0157

Volume 38 Issue 6

Feb. 2025

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Article Navigation > Nuclear Power Engineering > 2017 > 38(6): 157-162

Liu Yu, Tan Zhanglu, Pan Junjie, Wang Xiaoyu, Xu Liangjian, Deng Jian. Development of Self-reliant Subchannel Analysis Code CORTH[J]. Nuclear Power Engineering, 2017, 38(6): 157-162. doi: 10.13832/j.jnpe.2017.06.0157

Citation:

Liu Yu, Tan Zhanglu, Pan Junjie, Wang Xiaoyu, Xu Liangjian, Deng Jian. Development of Self-reliant Subchannel Analysis Code CORTH[J]. Nuclear Power Engineering, 2017, 38(6): 157-162. doi: 10.13832/j.jnpe.2017.06.0157

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Development of Self-reliant Subchannel Analysis Code CORTH

doi: 10.13832/j.jnpe.2017.06.0157

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

Received Date: 2017-08-25
Rev Recd Date: 2017-10-25

Available Online: 2025-02-09

Abstract

Abstract

CORTH is a subchannel code self-reliant developed by Nuclear Power Institute of China（NPIC） based on four equation model with slip ratio to perform thermal-hydraulic analysis of reactor cores or experimental facility with heating rod bundles. The development of CORTH adopted modular design and object-oriented programming method, and specially provided with graphic user interface for input deck preparing and output analysis. CORTH has been executed software testing by independent third organization to ensure the readability and standardization of coding. Testing data in NPPs, international benchmark and AP1000 nominal condition were used to carry out verifications and validations of CORTH. The results show the good accuracy of CORTH that meets the requirement of engineering design and analysis.
- Sub-channel analysis code,
- CORTH,
- Code development