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Solution of the neutron transport equation by the Method of Characteristics using a linear representation of the source within a mesh
Mazumdar, Tanay, Degweker, S.B.Volume:
108
Language:
english
Journal:
Annals of Nuclear Energy
DOI:
10.1016/j.anucene.2017.04.011
Date:
October, 2017
File:
PDF, 7.26 MB
english, 2017