Open AccessNUMERICAL SOLUTION OF TRANSIENT AND STEADY-STATE NEUTRON TRANSPORT PROBLEMS
Author(s) -
B.G. Carlson
Publication year - 1959
Language(s) - English
Resource type - Reports
DOI - 10.2172/4198642
Subject(s) - generality , neutron transport , transient (computer programming) , steady state (chemistry) , mathematics , neutron , convection–diffusion equation , computer science , physics , statistical physics , mathematical analysis , nuclear physics , chemistry , psychology , psychotherapist , operating system
A general numerical procedure, called the discrete S/sub n/ method, for solving the neutron transport equation is described. The main topics relate to the derivation of suitable difference equations, and to the problem of solving these, while maintaining generality, accuracy, and reasonable computing speed. A few comparisons with other methods are made. (auth