Grenade - A coarse-mesh reactor physics program to solve the static diffusion equation for neutrons

Published: 1 January 1986| Version 1 | DOI: 10.17632/g2j57d55z8.1
T.A. Beu, D.I. Simionovici, V.N. Anghel


Title of program: GRENADE Catalogue Id: AALJ_v1_0 Nature of problem The program is designed to solve the static multigroup diffusion equation for neutrons in multidimensional problems, assuming Cartesian geometry. The program yields flux- and power distributions and the effective neutron multiplication factor (keff). Versions of this program held in the CPC repository in Mendeley Data AALJ_v1_0; GRENADE; 10.1016/0010-4655(86)90037-8 This program has been imported from the CPC Program Library held at Queen's University Belfast (1969-2018)



Computational Physics, Reactor