Indentation creep of UO2 before and after irradiation
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
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 16024656
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CRACKS; CREEP; FUEL PELLETS; GRAIN BOUNDARIES; KNOOP HARDNESS; PERFORMANCE TESTING; PHYSICAL RADIATION EFFECTS; POST-IRRADIATION EXAMINATION; TEMPERATURE DEPENDENCE; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; MECHANICAL PROPERTIES; MICROSTRUCTURE; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; TESTING; URANIUM COMPOUNDS; URANIUM OXIDES