An analytical solution of multi-group removal-diffusion equations, in plane multi-layered, reactor shield system

Abstract

This paper gives the analytical solution of the set of differential equations describing, in the multigroup removal-diffusion approximation of Boltzmann's transport equation, the neutron flux distributions in the multi-layered plane shield of a nuclear reactor. The solution is obtained in closed form of a linear combination of some well-defined auxiliary expression, which can be easily integrated and differentiated.