Journal article
Determination of the optimal few-energy group structure for the Canadian Super Critical Water-cooled Reactor
Abstract
Most deterministic neutron transport codes implement the multi-group approximation theory to solve the linear Boltzmann equation by which the neutron flux and the interaction cross-sections are averaged over discretized energy groups. In order to further reduce the computational cost for large scale and/or time dependent problems, this multi-group information undergoes additional energy group condensation into the so-called few energy group …
Authors
Moghrabi A; Novog DR
Journal
Annals of Nuclear Energy, Vol. 115, , pp. 27–38
Publisher
Elsevier
Publication Date
5 2018
DOI
10.1016/j.anucene.2018.01.011
ISSN
0306-4549