Open AccessPOSTIRRADIATION EXAMINATION OF 17-4 PH STAINLESS STEEL CONTROL ROD DRIVE RACK FROM SM-1 REACTOR
Author(s) -
K. K. Klindt,
A.E. Richt,
W.C. Thurber
Publication year - 1961
Language(s) - English
Resource type - Reports
DOI - 10.2172/4829940
Subject(s) - oak ridge national laboratory , rack , stress corrosion cracking , materials science , metallography , control rod , pressurized water reactor , metallurgy , cracking , corrosion , radiochemistry , nuclear engineering , nuclear chemistry , composite material , chemistry , nuclear physics , engineering , mechanical engineering , microstructure , physics
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