Formulation of expressions to be programmed for the calculation of number densities
Author(s) -
F. E. Sullivan
Publication year - 1962
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4202332
Subject(s) - burnup , criticality , nuclear physics , fission , neutron , void (composites) , computational physics , neutron flux , nuclear engineering , physics , materials science , mathematics , engineering , composite material
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