Verification and validation of the fast reactor multi-group cross section processing code MGGC2.0
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摘要: 基于多群截面的确定论计算方法一直都是反应堆工程设计的重要方法，多群截面精度直接影响着反应堆物理计算的精度。为了产生快堆高精度的截面数据，华北电力大学开发了高精度截面处理程序MGGC2.0，对该程序进行了基准验证和确认。基于ENDF/B-Ⅶ.1库计算无限大均匀混合介质UO2、MOX、U-TRU-Zr燃料，将MGGC2.0与MCNP产生的宏观截面对比验证，验证了程序产生多群截面的精度，超细群宏观多群总截面与MCNP的参考解的相对偏差基本在5%以内。然后对俄罗斯快堆实验BFS97-1进行了计算，提出了针对多种燃料排布形式的燃料少群截面均匀化方法，利用MGGC2.0的碰撞概率法计算了燃料的少群截面数据，利用DIF3D程序进行堆芯计算，同时还对比了不同截面均匀化方法的结果。研究结果表明：对于BFS97-1，如果直接采用临界搜索产生的截面，DIF3D计算的有效增殖因数（keff）结果与MCNP计算的keff的绝对偏差为2.541×10−2，通过改进燃料轴向不均匀计算方法，使得偏差降到了5.0×10−4以下。针对BFS97-1、BFS97-2、BFS97-5和BFS97-6的计算结果与MCNP结果的偏差都在3.0×10−3以内，验证了程序产生多群和少群截面具有较高精度，可以满足工程设计要求。Abstract: The deterministic calculation method based on multi-group cross section has always been an important approach in the design of nuclear reactors. The accuracy of multi-group cross section directly affects the precision of nuclear reactor physics calculations. In order to generate high-precision cross section data for fast reactors, North China Electric Power University has developed the high-precision cross section processing code MGGC2.0. This paper conducts benchmark verification and validation of the code. The infinite homogeneous mixed media UO2, MOX, and U-TRU-Zr fuels are calculated based on the ENDF/B-VII.1 library, and the macroscopic cross section generated by MGGC2.0 are compared with those produced by MCNP to verify the accuracy of the program in generating multi-group cross section. The relative deviation of the macroscopic multi-group total cross section from the reference solution of MCNP is generally within 5%. Subsequently, calculations are performed for the Russian fast reactor experiment BFS97-1, and a homogenization method of the fuel few-group cross section for various fuel arrangement forms is proposed. The collision probability method in MGGC2.0 was used to calculate the few-group cross section data for the fuel, and DIF3D program was employed for core calculations. Additionally, this study compared the results obtained using different cross section homogenization methods. The research findings indicate that for BFS97-1, if the cross section generated directly by critical search are used, the absolute deviation of the keff calculated by DIF3D from the keff calculated by MCNP is 2.541×10−2. This paper improves the calculation method of axial fuel inhomogeneity, reducing the deviation to below 5.0×10−4. The deviations between the calculated results for BFS97-1, BFS97-2, BFS97-5, and BFS97-6 and the MCNP results are all within3.0×10−3, validating the high accuracy of the code in generating multi-group and few-group cross section, which meets the requirements of engineering design.
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表 1 UO2燃料组件核子密度
Table 1. Nuclear density of UO2 fuel assembly
fuel nuclide density/(10−30 cm−3) fuel nuclide density/(110−28 cm−3) 16O 1.73649 ×10−2Cr 1.38077 ×10−3235U 1.30237 ×10−3Ni 1.20226 ×10−3238U 7.38009 ×10−3Mo 1.11526 ×10−4Fe 5.54166 ×10−3Na 1.10164 ×10−2
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表 2 MOX燃料组件核子密度
Table 2. Nuclear density of MOX fuel assembly
fuel nuclide density/(10−28 cm−3) fuel nuclide density/(10−28 cm−3) 16O 1.42606 ×10−2242Pu 4.84251 ×10−7235U 1.51479 ×10−5Fe 5.54166 ×10−3238U 5.72980 ×10−3Cr 1.38077 ×10−3239Pu 1.06137 ×10−3Ni 1.20226 ×10−3240Pu 9.47823 ×10−5Mo 1.11526 ×10−4241Pu 6.04937 ×10−6Na 1.10164 ×10−2
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表 3 U-TRU-Zr燃料组件核子密度
Table 3. Nuclear density of U-TRU-Zr fuel assembly
fuel nuclide density/(10−28 cm−3) fuel nuclide density/10−28 cm−3 234U 4.43391 ×10−7242mAm 3.62657 ×10−6235U 1.18642 ×10−5243Am 3.90663 ×10−5236U 9.70944 ×10−7242Cm 2.19375 ×10−6238U 7.65004 ×10−3243Cm 2.11852 ×10−7237Np 1.82075 ×10−5244Cm 2.62236 ×10−5236Pu 1.93830 ×10−10245Cm 6.78483 ×10−6238Pu 4.56105 ×10−5246Cm 3.59912 ×10−6239Pu 8.60964 ×10−4Zr 2.83927 ×10−3240Pu 5.16516 ×10−4Fe 1.78888 ×10−2241Pu 7.55625 ×10−5Cr 2.65991 ×10−3242Pu 1.14180 ×10−4Ni 1.10296 ×10−4241Am 4.20849 ×10−5Mo 4.87956 ×10−4
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表 4 BFS97-1不同截面制作的结果对比
Table 4. Comparison of results obtained with different cross section for BFS97-1
device
namereference
value/MCNPMGGC2.0/DIF3D absolute deviation direct critical search
calculation1-D homogenization
methoddirect critical search
calculation1-D homogenization
methodBFS97-1 0.99573 0.97032 0.99566 −2.541×10−2 −7.0×10−5
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表 5 MGGC2.0一维均匀化方法的计算结果
Table 5. Calculation results under 1-D homogenization method for MGGC2.0
device name reference value/
MCNPMGGC2.0/DIF3D
1-D homogenization methodabsolute deviation BFS97-1 0.99573 0.99566 −7.0×10−5 BFS97-2 1.00086 1.00060 −2.6×10−4 BFS97-5 0.99667 0.99505 −1.62×10−3 BFS97-6 0.99798 1.00093 2.95×10−3
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