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。Abstract: To verify the accuracy and applicability of JMCT program, 56 models are selected from the International Handbook of Evaluated Criticality Safety Benchmark Experiments. Models are established in JLAMT, and the effective multiplication factors are calculated by JMCT and compared with the reference values and MCNP calculation results. The results show that the calculated values of JMCT are generally within three standard deviations of the reference values and the relative deviations between the JMCT calculation results and the reference values are generally less than 2%. The study has verified the accuracy and applicability of JMCT program to a certain extent, and it provides a reference for the subsequent application and verification of JMCT.
-
Key words:
- JLAMT /
- JMCT /
- highly enriched uranium models /
- validation and verification
-
表 1 模型选取分类情况
Table 1. Categorization of the benchmarking models selected
thermal intermediate fast mixed total 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 表 2 热谱模型描述
Table 2. Description of the thermal models
identifier description major fission nuclides major 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 表 3 中能能谱模型描述
Table 3. Description of the intermediate models
identifier description major fission nuclides major 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 表 4 快谱模型描述
Table 4. Description of the fast models
identifier description major fission nuclides major nonfissionable nuclides HEU-COMP-FAST-001 fuel cans configured in rectangular-pitched array U235, U238 C, H, O HEU-COMP-FAST-003 hexagonal tank with fuel tubes in square reflector tank U235, U238 O, C, H HEU-MET-FAST-001 unreflected set of concentric spherical shells U235, U238 N, O HEU-MET-FAST-003 tuballoy-reflected sphere U235, U238 − HEU-MET-FAST-004 sphere stands on the seat U235 C, H, O HEU-MET-FAST-008 part of symmetric spheres U235 Fe, Cu HEU-MET-FAST-009 part of symmetric spheres U235, U238 Be, Fe, Cu HEU-MET-FAST-011 sphere with two hemisphere shell U235, U238 C, H HEU-MET-FAST-012 part of symmetric spheres U235 Al, Cu, Fe HEU-MET-FAST-013 part of symmetric spheres U235, U238 Cu, Fe HEU-MET-FAST-014 part of symmetric spheres U235, U238 Al, Fe HEU-MET-FAST-015 two cylinder with axial holes U235, U238 Fe HEU-MET-FAST-018 hollow sphere U235, U238 C, Fe HEU-MET-FAST-019 hollow sphere with reflector U235, U238 C HEU-MET-FAST-020 sphere with reflector U235, U238 C, H HEU-MET-FAST-021 hollow sphere with reflectors U235, U238 C, Fe HEU-MET-FAST-022 hollow sphere with reflector U235, U238 C, Al, Cu HEU-MET-FAST-026 square arrangement of cylinders with reflectors U235, U238 C, H, Fe HEU-MET-FAST-028 sphere with reflector U235, U238 − 表 5 混合能谱模型描述
Table 5. Description of the mixed models
identifier description major fission nuclides major nonfissionable nuclides HEU-MET-MIXED-001 stacking of cylinders with reflector U235, U238 C, H, Ti, Fe HEU-MET-MIXED-003 six-region sphere U235 C, H HEU-MET-MIXED-006 stacking of cylinders U235, U238 C, H, Fe HEU-COMP-MIXED-001 fuel cans configured in rectangular-pitched array U235 C, Fe, H, O, C HEU-COMP-MIXED-003 complex cone configuration with fuel U235 O, Be, H, Zr, W, Al 表 6 热谱模型结果统计分析
Table 6. Statistical analysis of thermal model results
relative deviation of keff average minimum maximum JMCT results 0.006 55 0.000 41 0.018 91 MCNP results 0.005 46 0.000 26 0.014 78 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 average minimum maximum JMCT results 0.017 21 0.001 04 0.044 78 MCNP results 0.009 76 0.000 49 0.034 95 表 8 快谱模型结果统计分析
Table 8. Statistical analysis of fast model results
relative deviation of keff average minimum maximum JMCT results 0.003 22 0.000 08 0.012 00 MCNP results 0.004 30 0.000 00 0.026 19 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 average minimum maximum JMCT results 0.008 40 0.001 56 0.025 02 MCNP results 0.003 52 0.000 44 0.007 95 -
[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