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用综合核方法求解中子输运临界问题的误差分析

     

摘要

The Synthetic Kernel approximation method based on neutron integral transport equation possesses the characteristic of accuracy and speediness, and its computational accuracy and convergence depend on the choice of quadrature sets. The Synthetic Kernel method of solving neutron transport criticality problems is briefly introduced, and the computational error and convergence of the Synthetic Kernel approximation is analysed. The new quadrature sets are proposed to improve the computational accuracy of the Synthetic Kernel at low orders. Some one and two-energy neutron criticality problems in isotropic and linearly anisotropic scattering homogeneous us plane medium are tested, and the SK_N solutions are compared with the discrete ordinates method S_(32) solutions and the solutions in the literatures. The Synthetic Kernel approximation yields more accurate results even at low orders by using appropriate quadrature sets.%基于中子积分输运方程的综合核近似方法,具有准确、快速的特点,其计算精度和收敛性与求积组的选取密切相关.文章简要介绍了求解中子输运临界问题的综合核方法,采用数值方法分析了综合核近似的计算误差和收敛性,并提出了新的求积组来提高综合核方法的计算精度.应用综合核方法计算了均匀平板介质中各向同性和线性各向异性散射的单群、双群中子临界问题,并与离散纵标法S_(32)结果和文献结果进行了比较.计算结果表明采用合适的求积组,综合核方法在低阶时能够得到较高精度的结果.

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