| 压水堆燃料辐照性能多物理耦合并行分析程序开发 |
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| 引用本文： | 韩智杰,何晓军,明春,杨衍康,任帅,胡长军,杨文. 压水堆燃料辐照性能多物理耦合并行分析程序开发[J]. 原子能科学技术, 2021, 55(9): 1606-1612. DOI: 10.7538/yzk.2021.youxian.0349 |
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| 作者姓名： | 韩智杰 何晓军 明春 杨衍康 任帅 胡长军 杨文 |
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| 作者单位： | 中国原子能科学研究院 反应堆工程技术研究所，北京102413；北京科技大学，北京100083 |
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| 摘 要： | 核燃料元件是反应堆的核心部件，其性能影响反应堆的安全性与经济性，利用燃料元件性能分析程序开展燃料堆内稳态辐照性能分析对于燃料设计及安全评价具有重要意义。通过开发燃料温度分布、变形计算、裂变气体释放及内压等模型，结合燃料元件热工-力学多物理耦合计算分析耦合方案，基于先进并行计算方法构建了高性能并行化燃料性能分析程序Athena。利用典型商用压水堆核电站数据及同类程序计算结果进行了程序初步验证，结果表明Athena程序计算结果合理可靠。通过定义堆芯功率及热工水力边界条件，程序能够并行开展压水堆全堆芯燃料辐照性能分析，提高燃料辐照性能分析效率，是数值反应堆原型系统（CVR1.0）的重要组成。
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| 关 键 词： | 燃料元件 辐照性能分析 并行计算 |
Development of Multi-physical Parallel Code for PWR Fuel Irradiation Performance Analysis |
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| HAN Zhijie,HE Xiaojun,MING Chun,YANG Yankang,REN Shuai,HU Changjun,YANG Wen. Development of Multi-physical Parallel Code for PWR Fuel Irradiation Performance Analysis[J]. Atomic Energy Science and Technology, 2021, 55(9): 1606-1612. DOI: 10.7538/yzk.2021.youxian.0349 |
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| Authors: | HAN Zhijie HE Xiaojun MING Chun YANG Yankang REN Shuai HU Changjun YANG Wen |
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| Affiliation: | Division of Reactor Engineering Technology Research,China Institute of Atomic Energy, Beijing 102413, China;University of Science and Technology Beijing, Beijing 100083, China |
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| Abstract: | Nuclear fuel element is the key component of reactor, and its performance affects the safety and economy of reactor. It is of great significance for fuel design and safety analysis to carry out fuel element steady state irradiation performance predication using fuel performance analysis code. By developing fuel rod temperature, deformation, fission gas release and internal gas pressure calculation models, a high-performance parallel fuel performance analysis code Athena was built based on advanced parallel calculation method and thermal-mechanical multi-physical coupling scheme. The code was primarily verified by comparing the data of a typical commercial pressurized water reactor (PWR) nuclear power plant and the calculation results of similar code. The results show that Athena calculation results are reasonable and reliable. By defining the fuel power and thermal-hydraulic boundary conditions, the fuel performance analysis of the whole PWR core can be carried out to improve the efficiency. It is an important part of the numerical reactor prototype system (CVR1.0). |
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| Keywords: | fuel element irradiation performance analysis parallel computing |
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