Abstract:
The neutron transport SP
3 equation was solved by high order generalized transverse integration nodal method, this method was used to solve the neutron diffusion equation to eliminate the transverse leakage approximation in traditional transverse integration nodal method to improve numerical accuracy. Besides, the nodal interior neutron flux distribution information for this method can be used directly for core pin power reconstruction. The IAEA 2D/3D and LMW 3D benchmark problem are solved with this method. Numerical tests indicate that this method achieve higher accuracy than traditional nodal method and better pin power reconstruction result.