Benchmark Tests of Radiation Transport Computer Codes for Reactor Core and Shield Calculations

摘要

Aiming at providing test problems that may be used to verify an adequate perform-ance of the current version of a neutron and r-ray transport computer code used for reactor core or shield calculations, we summarize the input data and the calculated results for three benchmark problems.The 1st problem deals with a 1-dimensional small spherical reactor for use to test 1-dimensional SN codes, DTF-IV and ANISN, and possibly the MORSE Monte Carlo code. The 2nd problem concerned with 2-dimensional (x, y) neutron propagation through an absorbing medium gives a severe test for 2-dimensional SN codes, TWOTRAN-GG, TWOTRAN-II, DOT-3 and TRIPLET. The last problem dealing with 2-dimensional (r, z) radiation streaming is to test also the finite difference Sy codes, TWOTRAN-II and DOT-3, and the finite element Sy code FEMRZ. The present article summarizes also the general tendency of the effect of parameters used for these calculations on the numerical results and computation time.