Open AccessMaterials for Molten-Salt Reactors
Author(s) -
H.E. McCoy,
John R. Weir,
R.L. Beatty,
W. H. Cook,
C.R. Kennedy,
A.P. Litman,
R.E. Gehlbach,
C.E. Sessions,
J. W. Koger
Publication year - 1969
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/1457693
Subject(s) - graphite , molten salt reactor , molten salt , embrittlement , coolant , materials science , melting point , nuclear engineering , neutron flux , metallurgy , neutron , composite material , mechanical engineering , engineering , physics , nuclear physics
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