Open AccessHigh Fluency Low Flux Embrittlement Models of LWR Reactor Pressure Vessel Embrittlement and a Supporting Database from the UCSB ATR-2 Irradiation Experiment
Author(s) -
G.R. Odette
Publication year - 2017
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/1346148
Subject(s) - embrittlement , materials science , reactor pressure vessel , neutron flux , hardening (computing) , irradiation , metallurgy , microstructure , nuclear engineering , fluence , light water reactor , neutron , nuclear physics , composite material , physics , engineering , layer (electronics)
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