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Research on verification benchmarks for reactor thermal-hydraulic system analysis software.

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Τίτλος: Research on verification benchmarks for reactor thermal-hydraulic system analysis software.
Συγγραφείς: Gao, Xinli, Zhu, Guangyu, Du, Pingfei, Wang, Ke, Chen, Yiran, Zuo, Jiaxu, Zhang, Hao, Huang, Tao, Zhang, Kui, Chen, Ronghua, Xu, Caihong
Πηγή: International Journal of Advanced Nuclear Reactor Design & Technology; Sep2026, Vol. 8 Issue 3, p380-387, 8p
Θεματικοί όροι: Software verification, Benchmark testing (Engineering), Nuclear research, Benchmark problems (Computer science), Numerical analysis, Nuclear energy safety measures, Boundary value problems, Nuclear reactors
Γεωγραφικοί όροι: China
Περίληψη: Verification serves as the prerequisite for the engineering application of independently developed nuclear safety analysis software. Verification methods for reactor thermal-hydraulic system analysis software are studied, and the framework and workflow for verification were proposed. Based on the development and application of reactor thermal-hydraulic numerical algorithms, nine benchmark problems were identified and selected. Multiple nuclear power research institutions of China were invited to perform comparative calculations using independently developed software. Analysis of the computational results revealed the influence of factors such as boundary conditions, numerical algorithms, interphase friction, and virtual mass force on software verification results. Consequently, the boundary conditions and application requirements for the benchmark problems were standardized, the comparison and acceptance standards for the benchmark problems were unified, and the standards framework have been established for the verification work of China's independent developed reactor thermal-hydraulic system analysis software. [ABSTRACT FROM AUTHOR]
Copyright of International Journal of Advanced Nuclear Reactor Design & Technology is the property of Xi'an Jiaotong University Periodicals Center and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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  Data: Verification serves as the prerequisite for the engineering application of independently developed nuclear safety analysis software. Verification methods for reactor thermal-hydraulic system analysis software are studied, and the framework and workflow for verification were proposed. Based on the development and application of reactor thermal-hydraulic numerical algorithms, nine benchmark problems were identified and selected. Multiple nuclear power research institutions of China were invited to perform comparative calculations using independently developed software. Analysis of the computational results revealed the influence of factors such as boundary conditions, numerical algorithms, interphase friction, and virtual mass force on software verification results. Consequently, the boundary conditions and application requirements for the benchmark problems were standardized, the comparison and acceptance standards for the benchmark problems were unified, and the standards framework have been established for the verification work of China's independent developed reactor thermal-hydraulic system analysis software. [ABSTRACT FROM AUTHOR]
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  Data: <i>Copyright of International Journal of Advanced Nuclear Reactor Design & Technology is the property of Xi'an Jiaotong University Periodicals Center and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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        Value: 10.1016/j.jandt.2026.08.003
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        Text: English
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        Type: general
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              Text: Sep2026
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