| 稳态堆芯多物理耦合系统CSSS V1.0的研发 |
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| 引用本文： | 安萍,刘东,潘俊杰,赵文博,芦韡.稳态堆芯多物理耦合系统CSSS V1.0的研发[J].原子能科学技术,2019,53(5):863-868. |
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| 作者姓名： | 安萍 刘东 潘俊杰 赵文博 芦韡 |
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| 作者单位： | 1.中国核动力研究设计院，四川 成都610213；2.核反应堆系统设计技术重点实验室，四川 成都610213；3.中核集团核能软件与数字化反应堆工程技术研究中心，四川 成都610213 |
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| 摘 要： | 充分考虑反应堆堆芯中子学物理、热工水力、燃料等专业的相互耦合过程，将先进节块法堆芯中子学计算软件NACK V1.0、热工水力子通道软件CORTH V2.0、燃料棒性能分析软件FUPAC V1.1进行集成耦合，得到稳态堆芯多物理耦合模拟设计分析系统CSSS V1.0，可计算典型压水堆的稳态运行物理、热工、燃料等专业参数。通过NEACRP-L-335压水堆基准问题验证计算，CSSS V1.0系统的计算结果与国际基准PARCS程序总体符合较好。
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| 关 键 词： | 多物理耦合 先进节块法 热工水力分析 燃料棒性能分析 |
Development of Steady Reactor Core Multi-physics Coupling System CSSS V1.0 |
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| AN Ping,LIU Dong,PAN Junjie,ZHAO Wenbo,LU Wei.Development of Steady Reactor Core Multi-physics Coupling System CSSS V1.0[J].Atomic Energy Science and Technology,2019,53(5):863-868. |
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| Authors: | AN Ping LIU Dong PAN Junjie ZHAO Wenbo LU Wei |
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| Affiliation: | 1.Nuclear Power Institute of China, Chengdu 610213, China; 2.Science and Technology on Reactor System Design Technology Laboratory, Chengdu 610213, China;3.CNNC Engineering Research Center of Nuclear Energy Software and Digital Reactor, Chengdu 610213, China |
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| Abstract: | The reactor core is the coupled result of the multi-physics including the neutronics, thermal-hydraulics, fuel and so on. Coupling the advanced nodal core key program NACK V1.0, core thermal-hydraulic analysis program CORTH V2.0 and fuel rod performance analysis code FUPAC V1.1, the reactor core steady simulation system CSSS V1.0 was got. CSSS V1.0 was used to simulate typical pressurized water reactor core. The calculation result of pressurized water reactor benchmark problem NEACRP-L-335 shows that CSSS V1.0 is in good agreement with benchmark program PARCS. |
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| Keywords: | multi-physics coupling advanced nodal method thermal-hydraulic analysis fuel rod performance analysis |
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