| 六边形套管型燃料堆芯临界质量测量试验结果验证分析 |
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| 引用本文： | 魏彦琴,黄世恩,王连杰,娄磊,操节宝,蔡云.六边形套管型燃料堆芯临界质量测量试验结果验证分析[J].核动力工程,2022,43(1):238-241. |
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| 作者姓名： | 魏彦琴 黄世恩 王连杰 娄磊 操节宝 蔡云 |
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| 作者单位： | 中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213 |
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| 摘 要： | 为验证核设计程序对燃料组件、铍组件和铝组件的计算可靠性，对六边形套管型燃料堆芯（HCTFR）临界质量测量试验数据进行了验证计算和偏差分析。通过分析不同位置铝组件的反应性差异，提出了新的近活性区铝组件计算模型，将铝组件近活性区布置方案的计算偏差从2.2%降低至0.1%，为堆芯核设计程序的工程验证奠定了较好的基础。
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| 关 键 词： | 六边形套管型燃料堆芯 临界物理试验 临界质量测量 核设计程序 试验验证 |
| 收稿时间： | 2021-07-29 |
Validation and Analysis of Test Results of Critical Mass Measurement of Hexagonal Casing Type Fuel Reactor |
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| Wei Yanqin,Huang Shien,Wang Lianjie,Lou Lei,Cao Jiebao,Cai Yun.Validation and Analysis of Test Results of Critical Mass Measurement of Hexagonal Casing Type Fuel Reactor[J].Nuclear Power Engineering,2022,43(1):238-241. |
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| Authors: | Wei Yanqin Huang Shien Wang Lianjie Lou Lei Cao Jiebao Cai Yun |
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| Affiliation: | Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China |
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| Abstract: | In order to verify the calculation reliability of nuclear design code for fuel assembly, beryllium assembly and aluminum assembly, the verification calculation and deviation analysis of test data of critical mass measurement of hexagonal casing type fuel reactor are carried out. By analyzing the reactivity differences of aluminum assemblies in different locations, a new calculation model of aluminum assemblies near active zone is proposed, which reduces the calculation deviation of aluminum assemblies near active zone from 2.2% to 0.1%. It lays a good foundation for the engineering verification of the core nuclear design code. |
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| Keywords: | Hexagonal casing type fuel reactor(HCTFR) Critical physical experiment Critical mass measurement test Nuclear design code Experimental validation |
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