Published March 2002
| Version v1
Journal article
Thermal expansion of UO2 and simulated DUPIC fuel
Description
The lattice parameters of simulated DUPIC fuel and UO2 were measured from room temperature to 1273 K using neutron diffraction to investigate the thermal expansion and density variation with temperature. The lattice parameter of simulated DUPIC fuel is lower than that of UO2, and the linear thermal expansion of simulated DUPIC fuel is higher than that of UO2. For the temperature range from 298 to 1273 K, the average linear thermal expansion coefficients for UO2 and simulated DUPIC fuel are 10.471x10-6 and 10.751x10-6 K-1, respectively
Additional details
Identifiers
- PII
- S0022311501007127;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 301
- Journal Issue
- 2-3
- Journal Page Range
- p. 242-244
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Israel
- INIS RN
- 33063103
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- CANDU TYPE REACTORS; NEUTRON DIFFRACTION; PWR TYPE REACTORS; REACTOR LATTICE PARAMETERS; REACTOR LATTICES; REACTOR PHYSICS; SPENT FUELS; TEMPERATURE DEPENDENCE; THERMAL EXPANSION; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COHERENT SCATTERING; DIFFRACTION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPANSION; FUELS; HEAVY WATER MODERATED REACTORS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR MATERIALS; REACTORS; SCATTERING; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.