Reactor Statics Module, RS-9: Multigroup Diffusion Program Using an Exponential Acceleration Technique

Abstract

The nine Reactor Statics Modules are designed to introduce students to the use of numerical methods and digital computers for calculation of neutron flux distributions in space and energy which are needed to calculate criticality, power distribution, and fuel burnup for both slow neutron and fast neutron fission reactors. The last module, RS-9, includes a separate program, WANDIC (one-dimensional diffusion code with three energy-group representation), for the calculations of neutron spectra and group constants for use in fast breeder reactor calculations. It can be used with the criticality programs in RS-2 and RS-8. The reactor is divided into several concentric annular regions and it is assumed that those regions can be represented fairly well by their average properties. The previous modules show how these properties are found. The set of nine modules is intended to supplement textbooks and other lecture material generally available to students in their course work. It is assumed that students are familiar with elementary nuclear structure, neutron-nuclei interactions, and introductory material on fission chain reactors. (Author/SK)