Open AccessGraphical representation of neutron differential cross section data for reactor dosimetry applications. [Fission neutrons]
Author(s) -
D.L. Smith
Publication year - 1977
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/7300095
Subject(s) - dosimetry , neutron , differential (mechanical device) , fission , weighting , computer science , physics , mathematics , nuclear physics , nuclear medicine , medicine , acoustics , thermodynamics
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