SIMULATION OF THE ORSORT BUTTERMILK REACTOR, LOSS OF FUEL FLOW
Author(s) -
C.S. Walker
Publication year - 1958
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4333082
Subject(s) - cracking , swelling , materials science , fission , ultimate tensile strength , coolant , brittleness , nuclear fuel , mechanics , deformation (meteorology) , flow (mathematics) , nuclear engineering , creep , composite material , thermodynamics , neutron , engineering , physics , nuclear physics
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