Open AccessModeling of Complex Wear Behavior Associated with Grid-to-Rod Fretting in Light Water Nuclear Reactors
Author(s) -
Peter J. Blau,
Jun Qu,
Roger Y. Lu
Publication year - 2016
Publication title -
jom
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.67
H-Index - 107
eISSN - 1543-1851
pISSN - 1047-4838
DOI - 10.1007/s11837-016-2113-9
Subject(s) - fretting , cladding (metalworking) , nuclear fuel , materials science , nuclear engineering , coolant , light water reactor , fretting wear , pressurized water reactor , zirconium alloy , grid , nuclear reactor , metallurgy , oxide , zirconium , forensic engineering , mechanical engineering , engineering , geometry , mathematics
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