“TDMGDSA” A Two Dimensional Multigroup Diffusion Synthetic Accelerated Transport Code

Abstract

Neutron transport codes are essential tools in nuclear reactor and shielding design. Transport codes implement an iterative technique that suffers from slow convergence while solving highly scattering problems. This necessitated the development of acceleration methods, among which, the diffusion synthetic acceleration (DSA) is the fastest and the only stable method.In this paper we present the development of “TDMGDSA”, a two dimensional multi-group diffusion synthetic accelerated neutron transport computer code. TDMGDSA implements DSA to solve the discrete ordinate equations in X–Y geometry for three spatial differencing schemes; the diamond, weighted diamond, and linear discontinuous differencing. TDMGDSA is the first to implement a linear form of DSA for the diamond differencing, and is one of the first to implement DSA for the weighted diamond and linear discontinuous differencing schemes. TDMGDSA has been tested and is shown to be working reliably.