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Interaction Between UO 2 Pellets and Cladding in Water Reactor Fuel Pins
Author(s) -
WADDINGTON J. S.,
ROBERTS GEOFFREY,
DICKSON I. K.
Publication year - 1977
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.1151-2916.1977.tb15516.x
Subject(s) - cladding (metalworking) , pellets , materials science , creep , nuclear engineering , pressurized water reactor , composite material , engineering
The contribution of mechanical interaction between fuel and cladding to the change in length of a fuel pin has been identified from an analysis of data from the Steam‐Generating Heavy‐Water Reactor. A model which accounts for this effect uses the creep properties of fuel and cladding.