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Densification in Irradiated UO 2 Fuel
Author(s) -
Hastings Ian J.,
Fehrenbach Paul J.,
Hosbons Robert R.
Publication year - 1984
Publication title -
journal of the american ceramic society
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.9
H-Index - 196
eISSN - 1551-2916
pISSN - 0002-7820
DOI - 10.1111/j.1151-2916.1984.tb09613.x
Subject(s) - irradiation , materials science , uranium dioxide , nuclear engineering , radiochemistry , analytical chemistry (journal) , uranium , chemistry , nuclear physics , metallurgy , physics , engineering , chromatography
A densifcation algorithm for irradiated UO 2 fuel, modified to reflect a rapid densification rate from 0 to 10 MW.h/kg U, is presented. Included in a fuel performance code, the algorithm gives improved agreement between measured and calculated sheath strains.