Boiling-Water Reactor internals aging degradation study. Phase 1
Author(s) -
K.H. Luk
Publication year - 1993
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/10182155
Subject(s) - nuclear engineering , boiling water reactor , coolant , stress corrosion cracking , materials science , reactor pressure vessel , environmental science , boiler feedwater , neutron flux , natural circulation , nuclear reactor , boiling , shutdown , pressurized water reactor , neutron , corrosion , metallurgy , waste management , nuclear physics , mechanical engineering , engineering , boiler (water heating) , chemistry , physics , organic chemistry
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