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JMCT的高浓铀模型验证计算

史博 刘晓波

史博, 刘晓波. JMCT的高浓铀模型验证计算[J]. 强激光与粒子束, 2022, 34: 026008. doi: 10.11884/HPLPB202234.210352
引用本文: 史博, 刘晓波. JMCT的高浓铀模型验证计算[J]. 强激光与粒子束, 2022, 34: 026008. doi: 10.11884/HPLPB202234.210352
Shi Bo, Liu Xiaobo. The validation and calculation of highly enriched uranium models in JMCT[J]. High Power Laser and Particle Beams, 2022, 34: 026008. doi: 10.11884/HPLPB202234.210352
Citation: Shi Bo, Liu Xiaobo. The validation and calculation of highly enriched uranium models in JMCT[J]. High Power Laser and Particle Beams, 2022, 34: 026008. doi: 10.11884/HPLPB202234.210352

JMCT的高浓铀模型验证计算

doi: 10.11884/HPLPB202234.210352
详细信息
    作者简介:

    史 博,1279806784@qq.com

    通讯作者:

    刘晓波,13881190590@163.com

  • 中图分类号: TL329

The validation and calculation of highly enriched uranium models in JMCT

  • 摘要: 为了对JMCT程序的准确性和适用性进行验证,从国际临界基准库中选取了56个模型,通过使用JLAMT程序进行建模,然后利用JMCT程序计算了模型的有效增殖因子,并与基准值、MCNP程序计算结果进行对比。计算结果表明,JMCT计算值基本都在基准值的3倍标准差以内,且JMCT计算结果和基准值的相对偏差基本都在2%以下。在一定程度上验证了JMCT程序的准确性和适用性,为后续JMCT程序的使用验证提供借鉴。
  • 图  1  热谱模型计算结果

    Figure  1.  Results of thermal model calculation

    图  2  中能能谱模型计算结果

    Figure  2.  Results of intermediate model calculattion

    图  3  快谱模型计算结果

    Figure  3.  Results of fast model calculation

    图  4  混合能谱模型计算结果

    Figure  4.  Results of mixed model calculation

    表  1  模型选取分类情况

    Table  1.   Categorization of the benchmarking models selected

    thermalintermediatefastmixedtotal
    metal 6 5 17 3 31
    compound 6 3 2 2 13
    solution 8 2 0 0 10
    miscellaneous 2 0 0 0 2
    total 22 10 19 5 56
    下载: 导出CSV

    表  2  热谱模型描述

    Table  2.   Description of the thermal models

    identifierdescriptionmajor fission nuclidesmajor nonfissionable nuclides
    HEU-MET-THERM-001 stacking of square plates U235, U238 Si, C, H, O
    HEU-MET-THERM-006 lattices of square fuel elements U235, U238 H, O
    HEU-MET-THERM-007 square arrangement of fuel elements U235, U238 Fe, Cr, H, O
    HEU-MET-THERM-009 stacking of square plates U235, U238 Mg, C, H, O
    HEU-MET-THERM-011 rectangular basket with built-in fuel plates U235, U238 H, O, Al
    HEU-MET-THERM-012 stacking of square plates U235, U238 C, H
    HEU-COMP-THERM-001 square arrangement of fuel cans U235, U238 C, H, O
    HEU-COMP-THERM-003 arrangement of cross-shaped fuel rod U235, U238 C, H, O, Cu
    HEU-COMP-THERM-005 hexagonal arrangement of fuel cluster U235, U238 C, H, O, Cu
    HEU-COMP-THERM-007 arrangement of cross-shaped fuel rod U235, U238 C, H, O, Zr, Cu
    HEU-COMP-THERM-010 fuel-pin arrays in water U235, U238 H, O, Be
    HEU-COMP-THERM-012 square arrangement of fuel rods U235, U238 H, O, Si
    HEU-SOL-THERM-001 unreflected tanks filled with uranyl nitrate U235, U238 H, O, N
    HEU-SOL-THERM-003 plexiglas reflected tanks filled with uranyl nitrate U235 H, O, N, C
    HEU-SOL-THERM-005 cylindrical tank filled with fission solution U235, U238 H, O, N, B, Si
    HEU-SOL-THERM-007 concrete-reflected arrays of tanks filled with fission solution U235 N, H, O, C, Al, Cr, Fe
    HEU-SOL-THERM-009 sphere with a fuel region U235 H, O, F, Al
    HEU-SOL-THERM-011 sphere with a fuel region U235 H, O, F, Al
    HEU-SOL-THERM-013 sphere with a fuel region U235, U238 H, O, N, Al
    HEU-SOL-THERM-032 sphere containing uranyl nitrate U235, U238 H, O, N, Al
    HEU-MISC-THERM-001 lattices of square fuel elements U235, U238 H, O, B, N
    HEU-MISC-THERM-002 lattices of fuel pins U235, U238 B, N, O, H
    下载: 导出CSV

    表  3  中能能谱模型描述

    Table  3.   Description of the intermediate models

    identifierdescriptionmajor fission nuclidesmajor nonfissionable nuclides
    HEU-MET-INTER-001 stacking of core fuel plates U235, U238 Fe, Cr
    HEU-MET-INTER-002 stacking of cylindrical plates U235, U238 C, H, Ti
    HEU-MET-INTER-003 stacking of cylinders with reflector U235, U238 Be, O
    HEU-MET-INTER-004 stacking of cylinders with reflector U235, U238 C, H
    HEU-MET-INTER-008 assemblies of cylindrical tubes U235, U238, Th232 C, H, O, Al
    HEU-COMP-INTER-001 complex cone configuration with fuel U235 O, Be, H, Zr, W, Al
    HEU-COMP-INTER-003 cylindrical arrangement of component parts U235, U238 H, O, N, Be, C
    HEU-COMP-INTER-006 hexagonal tank with fuel tubes in square reflector tank U235, U238 O, H, C
    HEU-SOL-INTER-001 four-region sphere U235 H, O, F
    HEU-SOL-INTER-002 three-region sphere with critical height fuel solution U235, U238 H, O, F, Fe, C
    下载: 导出CSV

    表  4  快谱模型描述

    Table  4.   Description of the fast models

    identifierdescriptionmajor fission nuclidesmajor nonfissionable nuclides
    HEU-COMP-FAST-001fuel cans configured in rectangular-pitched arrayU235, U238C, H, O
    HEU-COMP-FAST-003hexagonal tank with fuel tubes in square reflector tankU235, U238O, C, H
    HEU-MET-FAST-001unreflected set of concentric spherical shellsU235, U238N, O
    HEU-MET-FAST-003tuballoy-reflected sphereU235, U238
    HEU-MET-FAST-004sphere stands on the seatU235C, H, O
    HEU-MET-FAST-008part of symmetric spheresU235Fe, Cu
    HEU-MET-FAST-009part of symmetric spheresU235, U238Be, Fe, Cu
    HEU-MET-FAST-011sphere with two hemisphere shellU235, U238C, H
    HEU-MET-FAST-012part of symmetric spheresU235Al, Cu, Fe
    HEU-MET-FAST-013part of symmetric spheresU235, U238Cu, Fe
    HEU-MET-FAST-014part of symmetric spheresU235, U238Al, Fe
    HEU-MET-FAST-015two cylinder with axial holesU235, U238Fe
    HEU-MET-FAST-018hollow sphereU235, U238C, Fe
    HEU-MET-FAST-019hollow sphere with reflectorU235, U238C
    HEU-MET-FAST-020sphere with reflectorU235, U238C, H
    HEU-MET-FAST-021hollow sphere with reflectorsU235, U238C, Fe
    HEU-MET-FAST-022hollow sphere with reflectorU235, U238C, Al, Cu
    HEU-MET-FAST-026square arrangement of cylinders with reflectorsU235, U238C, H, Fe
    HEU-MET-FAST-028sphere with reflectorU235, U238
    下载: 导出CSV

    表  5  混合能谱模型描述

    Table  5.   Description of the mixed models

    identifierdescriptionmajor fission nuclidesmajor nonfissionable nuclides
    HEU-MET-MIXED-001stacking of cylinders with reflectorU235, U238C, H, Ti, Fe
    HEU-MET-MIXED-003six-region sphereU235C, H
    HEU-MET-MIXED-006stacking of cylindersU235, U238C, H, Fe
    HEU-COMP-MIXED-001fuel cans configured in rectangular-pitched arrayU235C, Fe, H, O, C
    HEU-COMP-MIXED-003complex cone configuration with fuelU235O, Be, H, Zr, W, Al
    下载: 导出CSV

    表  6  热谱模型结果统计分析

    Table  6.   Statistical analysis of thermal model results

    relative deviation of keff
    averageminimummaximum
    JMCT results 0.006 55 0.000 41 0.018 91
    MCNP results 0.005 46 0.000 26 0.014 78
    下载: 导出CSV

    表  7  中能能谱模型结果统计分析

    Table  7.   Statistical analysis of intermediate model results

    relative deviation of keff
    averageminimummaximum
    JMCT results 0.017 21 0.001 04 0.044 78
    MCNP results 0.009 76 0.000 49 0.034 95
    下载: 导出CSV

    表  8  快谱模型结果统计分析

    Table  8.   Statistical analysis of fast model results

    relative deviation of keff
    averageminimummaximum
    JMCT results 0.003 22 0.000 08 0.012 00
    MCNP results 0.004 30 0.000 00 0.026 19
    下载: 导出CSV

    表  9  混合能谱模型结果统计分析

    Table  9.   Statistical analysis of mixed model results

    relative deviation of keff
    averageminimummaximum
    JMCT results 0.008 40 0.001 56 0.025 02
    MCNP results 0.003 52 0.000 44 0.007 95
    下载: 导出CSV
  • [1] 李云龙, 杨海峰, 易璇, 等. JMCT程序临界安全基准校验计算与分析[J]. 强激光与粒子束, 2017, 29:016007. (Li Yunlong, Yang Haifeng, Yi Xuan, et al. Critical safety benchmark verification calculation and analysis of JMCT program[J]. High Power Laser and Particle Beams, 2017, 29: 016007
    [2] Blair B J, Rugama Y, Thompson M A, et al. International handbook of evaluated criticality safety benchmark experiments[M]. Paris France: Organization for Economic Cooperation and Development, Nuclear Energy Agency, 2006.
    [3] 李刚, 张宝印, 邓力, 等. 蒙特卡罗粒子输运程序JMCT研制[J]. 强激光与粒子束, 2013, 25(1):158-162. (Li Gang, Zhang Baoyin, Deng Li, et al. Development of Monte Carlo particle transport program JMCT[J]. High Power Laser and Particle Beams, 2013, 25(1): 158-162
    [4] 马彦, 付元光, 秦桂明, 等. 面向领域的大规模可视建模工具JLAMT的设计与实现[J]. 计算物理, 2016, 33(5):606-612. (Ma Yan, Fu Yuanguang, Qin Guiming, et al. Design and implementation of JLAMT, a domain-oriented large-scale visual modeling tool[J]. Chinese Journal of Computational Physics, 2016, 33(5): 606-612
    [5] 邓力, 李瑞, 丁谦学, 等. 基于JMCT秦山核电厂一期反应堆屏蔽计算与分析[J]. 核动力工程, 2021, 42(2):173-179. (Deng Li, Li Rui, Ding Qianxue, et al. Qinshan-I reactor shielding simulation and sensitivity analysis based on JMCT Monte Carlo code[J]. Nuclear Power Engineering, 2021, 42(2): 173-179
    [6] 付元光, 马彦, 上官丹骅, 等. 基于JMCT的大亚湾核电站反应堆精细建模与计算[J]. 核动力工程, 2014, 35(S2):239-241. (Fu Yuanguang, Ma Yan, Shang Guan Danhua, et al. Sophisticated modeling and calculation of Daya Bay nuclear power station reactor based on JMCT[J]. Nuclear Power Engineering, 2014, 35(S2): 239-241
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出版历程
  • 收稿日期:  2021-08-13
  • 修回日期:  2021-10-25
  • 录用日期:  2021-11-02
  • 网络出版日期:  2022-01-12
  • 刊出日期:  2022-01-11

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