六边形套管型燃料堆芯临界质量测量试验结果验证分析

Validation and Analysis of Test Results of Critical Mass Measurement of Hexagonal Casing Type Fuel Reactor

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

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。
- 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
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.
- Hexagonal casing type fuel reactor(HCTFR) /
- Critical physical experiment /
- Critical mass measurement test /
- Nuclear design code /
- Experimental validation

图 1 附加区在外区的超栅元计算模型

Figure 1. Super-Cell Computing Model with External Additional Area

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图 2 附加区在内区的超栅元计算模型

Figure 2. Super-Cell Computing Model with Internal Additional Area

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表 1 临界质量测量试验方案信息

Table 1. Information of Test Program of Critical Mass Measurement　　　

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表 2 附加区设置

Table 2. Additional Area Settings

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表 3 临界质量测量试验堆芯k_eff验证计算结果

Table 3. k_eff Verification Calculation Results of Critical Mass Measurement Test Core

方案	试验值	计算结果	相对偏差/%^①
1	1.00000	1.00294	0.3
2	1.00173	0.99752	−0.4
3	1.00028	0.99262	−0.8
4	1.00039	0.99528	−0.5
5	1.00004	1.02201	2.2
5	1.00004	1.00071^②	0.1
6	1.00014	0.98967	−1.0
注：①相对偏差=[(计算结果−试验值)/试验值]×100%；②使用近活性区铝组件计算模型的结果

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