Open AccessStress analysis of pressurized water reactor steam generator tube denting phenomena. Interim report
Author(s) -
J. M. Thomas,
R. C. Cipolla,
G. V. Ranjan,
G. Derbalian
Publication year - 1978
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/6803020
Subject(s) - tube (container) , materials science , deformation (meteorology) , cracking , stress corrosion cracking , pressurized water reactor , corrosion , composite material , volume (thermodynamics) , metallurgy , engineering , nuclear engineering , physics , quantum mechanics
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