基于VENUS-Ⅱ基准模型的SuperMC程序验证

李阳; 郝丽娟; 邹俊; 宋婧; 程梦云

doi:10.11884/HPLPB201830.170218

基于VENUS-Ⅱ基准模型的SuperMC程序验证

doi: 10.11884/HPLPB201830.170218

李阳^{1, 2,},
郝丽娟¹,
邹俊¹,
宋婧¹,
程梦云^1, ,

1.
中国科学院核能安全技术研究所, 中子输运理论与辐射安全重点实验室, 合肥 230031
2.
中国科学技术大学, 合肥 230026

基金项目:

国家自然科学基金项目 11405204

中国科学院国防科技创新基金项目 CXJJ-17M175

详细信息

作者简介:
李阳(1991—)，男，硕士研究生，核科学与工程专业，从事核反应堆堆芯物理分析; yang.li3@fds.org.cn

通讯作者:
程梦云(1979—)，女，博士，核科学与工程专业，从事核技术应用研究; mengyun.cheng@fds.org.cn

中图分类号: TL329
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- 被引次数: 0
出版历程
- 收稿日期: 2017-06-20
- 修回日期: 2017-08-31
- 刊出日期: 2018-01-15

Validation of SuperMC based on VENUS-Ⅱ benchmark experiment

Li Yang^{1, 2
,},
Hao Lijuan¹,
Zou Jun¹,
Song Jing¹,
Cheng Mengyun^{1
, ,}

1.
Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China
2.
University of Science and Technology of China, Hefei 230026, China

摘要

摘要: 为了验证SuperMC软件系统对装载MOX燃料压水堆的临界计算能力，采用国际经合组织核能署(OECD/NEA)2001年发布的三维VENUS-Ⅱ国际基准模型对SuperMC3.1版本进行了测试验证。本次测试包括栅元和堆芯两个部分，分别计算了栅元无限增殖因数、重核反应率、堆芯有效增殖因数、堆芯轴向裂变反应率等关键物理参数。将SuperMC计算结果与基准模型实验测量值以及MCNP计算值作了对比。结果显示：在测试范围内，SuperMC计算值与参考值吻合得较好，表明SuperMC可应用于含MOX燃料堆芯的临界计算。
- SuperMC /
- VENUS-Ⅱ基准模型 /
- 蒙特卡罗 /
- MOX燃料 /
- 测试验证
Abstract: Super Monte Carlo Program for Nuclear and Radiation Simulation (SuperMC), a general, intelligent, accurate and precise simulation software system for the design and safety evaluation of nuclear systems, is developed by FDS team of key laboratory of neutronics and radiation safety. In order to validate the accuracy of SuperMC in calculating MOX-fueled system, it was benchmarked with the VENUS-Ⅱ MOX-fueled core model released by OECD/NEA. Both cell and core calculations were performed. A series of key parameters of cell infinite multiplication factor, reaction rates per heavy isotope, core effective multiplication factor, and axial fission rate distribution of six fuel pins were calculated. The computational results are compared with measured data and the MCNP calculated results, showing that the SuperMC results agree well with the experimental results and the MCNP calculated results. The correctness and reliability of SuperMC calculating neutron transport in MOX-fuelled system are preliminarily verified.
- SuperMC /
- VENUS-Ⅱ benchmark /
- Monte Carlo /
- MOX fuel /
- validation

HTML全文

图 1 VENUS-Ⅱ堆芯几何示意图

Figure 1. VENUS-Ⅱ core geometry

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图 2 被测量燃料栅元在堆芯中的位置

Figure 2. Measured and interpolated pin power position in VENUS-Ⅱ

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图 3 栅元模型SuperMC建模图

Figure 3. SuperMC model of fuel cells used for cell calculations

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图 4 VENUS-Ⅱ堆芯模型SuperMC建模图

Figure 4. Sectional view of VENUS-Ⅱ modeled by SuperMC

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图 5 3.3/0 UO₂燃料栅元中核素反应率SuperMC和MCNP计算结果对比

Figure 5. Deviations of reaction rates in 3.3/0 UO₂ fuel pin calculated by SuperMC from MCNP values

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图 6 4.0/0 UO₂燃料栅元中核素反应率SuperMC和MCNP计算结果对比

Figure 6. Deviations of reaction rates in 4.0/0 UO₂ fuel pin calculated by SuperMC from MCNP values

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图 7 2.2/2.7 MOX燃料栅元中核素反应率SuperMC和MCNP计算结果对比

Figure 7. Deviations of reaction rates in 2.2/2.7 MOX fuel pin calculated by SuperMC from MCNP values

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图 8 栅元轴向裂变率分布程序计算值与实验值比较

Figure 8. Comparison of calculated values and experimental values for axial fission rates distribution

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表 1 栅元k_∞计算结果比较

Table 1. k_∞ values of cell calculations

fuel cell	k_∞				deviation range*/%
fuel cell	MCNP	CosMC	TRIPOLI	SuperMC	deviation range*/%
3.3/0 UO₂	1.414 82±11 pcm	1.406 16±13.5 pcm	1.412 38±6 pcm	1.414 75±11 pcm	0.005~0.612
4.0/0 UO₂	1.344 25±11 pcm	1.338 72±13.5 pcm	1.341 22±7 pcm	1.344 12±11 pcm	0.001~0.403
2.2/2.7 MOX	1.272 49±13 pcm	1.260 24±13.5 pcm	1.269 44±6 pcm	1.272 57±13 pcm	0.006~0.978
* This column stands for the deviation of SuperMC relative to other MC codes in the table

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表 2 堆芯k_eff计算结果比较

Table 2. k_eff values of core calculation

item	k_eff	deviation/%
experimental	1.000 00±32 pcm
MCNP	1.001 32±9 pcm	0.132
COSMC	0.996 475±18.6 pcm	-0.353
TRIPOLI	1.004 07±6 pcm	0.407
superMC	1.001 45±9 pcm	0.164

下载: 导出CSV

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