Open AccessAn assessment of the failure rate for the beltline region of PWR pressure vessels during normal operation and certain transient conditions. Technical report
Author(s) -
Robert J. Gamble,
J. Strosnider
Publication year - 1981
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/5590178
Subject(s) - pressurized water reactor , transient (computer programming) , pressure vessel , nuclear engineering , nuclear reactor , reactor pressure vessel , process (computing) , failure rate , fracture (geology) , materials science , mechanics , environmental science , engineering , reliability engineering , computer science , physics , composite material , operating system
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