Dahua Hao1, Qiqing Liu1, Yin Yu1, Yile Hu1,*
The International Conference on Computational & Experimental Engineering and Sciences, Vol.26, No.2, pp. 1-1, 2023, DOI:10.32604/icces.2023.09301
Abstract In this study, a method for solving multigroup neutron diffusion equations for nuclear fuel pellets is
proposed based on the bond-based PeriDynamic (PD) theory. Firstly, adopting the idea of non-local
diffusion, the PD neutron diffusion coefficient is defined and calibrated through the equality of potential
with the traditional neutron diffusion coefficient. Comparing the calculation results of the neutron flux
distribution of the single-group neutron diffusion by the PD method and the traditional finite element
method, the feasibility of the method is verified. Secondly, apply the leakage term in single-group to multigroup and consider the scattering term between different energy groups.… More >
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