Open AccessTHE MATERIALS TESTING REACTOR DESIGN
Author(s) -
J.R. Huffman
Publication year - 1953
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4406959
Subject(s) - burnup , control rod , neutron flux , mechanics , beryllium , prompt neutron , mockup , materials science , nuclear reactor core , radiation flux , optics , nuclear engineering , computational physics , neutron , nuclear physics , physics , neutron temperature , delayed neutron , radiation , composite material , engineering
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