Author(s)

Masafumi Itagaki, Takeaki Enoto & Masakuni Narita

Abstract

A three-dimensional multiple reciprocity boundary element code has been developed in order to analyze the nuclear criticality of solution fuel systems in a reprocessing plant. The code solves the three-dimensional, two-group neutron diffusion equation as an eigenvalue problem. The boundary integral equation, the zero-order and higher order fundamental solutions for the multiple reciprocity scheme are all 2 X 2 matrix forms. The eigenvalue, which is successively updated through the power iterative computation, is also calculated using only boundary integrals. Test calculations demonstrate that the present method provides stable and accurate solution for

Keywords