Published January 1984 | Version v1
Journal article

Indentation creep of UO2 before and after irradiation

  • 1. Nagoya Univ. (Japan). Faculty of Engineering

Description

Measurements of creep by the indentation with Knoop indenter were performed for sintered UO2 pellets before and after irradiation and a non-irradiated single crystal with an applied load of 50 g. Room temperature creep of non-irradiated sinters included grain boundary sliding. The creep at the lowest dose (7.8 x 1014 fiss./cm3) also involved the grain boundary sliding, while no creep was observed after irradiation of 2.9 x 1015 fiss./cm3. Irradiated sinters at a dose between 1.4 x 1016 and 1 x 1018 fiss./cm3 yielded not only primary creep without the grain boundary sliding but also secondary creep, in which cracks were formed when a dose was less than 4.8 x 1017 fiss./cm3. At a dose of 1 x 1018 fiss./cm3 the enhanced secondary creep independent of the temperature between 100 and 1500C was observed. (author)

Additional details

Publishing Information

Journal Title
J. Nucl. Sci. Technol. (Tokyo)
Journal Volume
21
Journal Issue
1
Series
J. Nucl. Sci. Technol. (Tokyo).
Journal Page Range
42-55
ISSN
0022-3131