Open AccessInvestigating the flux-reduction option in reactor-vessel integrity. [PWR]
Author(s) -
D.G. Franklin,
T.U. Marston
Publication year - 1983
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/6174898
Subject(s) - embrittlement , reactor pressure vessel , neutron flux , nuclear engineering , pressure vessel , materials science , flux (metallurgy) , pressurized water reactor , reduction (mathematics) , environmental science , neutron , engineering , nuclear physics , metallurgy , composite material , physics , geometry , mathematics
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