Open AccessSpent thermal reactor fuel assembly characterization with solid state tract recorders
Author(s) -
R. Gold,
F.H. Ruddy,
E.P. Lippincott,
W.N. McElroy,
J.H. Roberts
Publication year - 1979
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/5944874
Subject(s) - neutron flux , nuclear engineering , neutron , neutron temperature , research reactor , spent nuclear fuel , radiochemistry , materials science , flux (metallurgy) , dosimeter , nuclear fuel , nuclear physics , chemistry , radiation , physics , engineering , metallurgy
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