Irradiation-induced creep in fuel compacts for high-temperature reactor applications
Creators
- 1. Stichting Energieonderzoek Centrum Nederland, Petten
Description
Restrained shrinkage experiments at neutron fluences up to 3 x 1021 n cm-2 DNE in the temperature range 600 to 12000C were performed on three different dummy coated-particle fuel compacts in the high-flux reactor at Petten. The data were evaluated to obtain the steady-state radiation creep coefficient of the compacts. It was found that, for the materials investigated, the creep coefficient is temperature dependent, but no clear relationship with Young's modulus could be established. Under certain conditions this irradiation-induced plasticity influences the elastic properties, with the concomitant increase of the creep coefficient. This effect coincides with the formation and further opening up of cracks due to stresses caused by irradiation-induced shrinkage of matrix material. (author)
Additional details
Publishing Information
- Journal Title
- High Temp. - High Pressures
- Journal Volume
- 9
- Journal Issue
- 2
- Series
- High Temp. - High Pressures.
- Journal Page Range
- 163-167
Conference
- Title
- 2. international carbon conference 'Carbon '76'.
- Dates
- 27 Jun - 2 Jul 1976.
- Place
- Baden-Baden, Germany, F.R.
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 9370235
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COATED FUEL PARTICLES; COMPACTS; CRACKS; CREEP; DAMAGING NEUTRON FLUENCE; HFR REACTOR; HIGH TEMPERATURE; MATRIX MATERIALS; PHYSICAL RADIATION EFFECTS; PLASTICITY; STRESSES; TEMPERATURE DEPENDENCE; VERY HIGH TEMPERATURE; YOUNG MODULUS
- Descriptors DEC
- ELASTICITY; ENRICHED URANIUM REACTORS; FUEL PARTICLES; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; NEUTRON FLUENCE; RADIATION EFFECTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS