| 超临界水堆堆芯轴向一维物理热工耦合稳态分析 |
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| 引用本文： | 刘占权,蒋朱敏,蒋校丰,王涛,张少泓. 超临界水堆堆芯轴向一维物理热工耦合稳态分析[J]. 核科学与工程, 2009, 29(1) |
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| 作者姓名： | 刘占权 蒋朱敏 蒋校丰 王涛 张少泓 |
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| 作者单位： | 上海交通大学核科学与工程学院,上海,200240;上海交通大学核科学与工程学院,上海,20024 |
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| 基金项目： | 国家重点基础研究发展规划(973计划) |
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| 摘 要： | 为研究超临界水冷堆堆芯可能存在的流动和核热耦合不稳定性问题,本文建立了简化的堆芯轴向一维单通道物理-热工耦合稳态分析模型,并针对文献给出的美国超临界水堆参考设计方案进行了稳态堆芯参数的计算,得出了和文献相一致的结论,为下一步开展超临界水堆核热耦合稳定性研究打下了基础.
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| 关 键 词： | 超临界水堆 核热耦合 一维 稳态 分析 |
Neutronics/thermal-hydraulics coupled axial 1D model for SCWR core static analysis |
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| LIU Zhan-quan,JIANG Zhu-min,JIANG Xiao-feng,WANG Tao,ZHANG Shao-hong. Neutronics/thermal-hydraulics coupled axial 1D model for SCWR core static analysis[J]. Chinese Journal of Nuclear Science and Engineering, 2009, 29(1) |
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| Authors: | LIU Zhan-quan JIANG Zhu-min JIANG Xiao-feng WANG Tao ZHANG Shao-hong |
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| Affiliation: | School of Nuclear Science and Engineering;Shanghai Jiao Tong University;Shanghai 200240;China |
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| Abstract: | In order to study the issue of stability that may exist in SCWR core caused by fluid flow and neutronics/TH coupling,a simplified axial 1D single channel model is developed to do neutronics/thermal-hydraulics coupled SCWR core analysis.The United States SCWR reference core design is studied and results obtained are found to be comparable to the reference ones.Further transient studies on SCWR stability are carrying on based on this static model. |
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| Keywords: | supercritical water reactor neutronics/thermal hydraulics coupling one-dimensional static analysis |
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