Thermal conductivity of hyperstoichiometric SIMFUEL
Creators
- 1. Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.
- 2. European Commission, Joint Research Centre, European Institute for Transuranium Elements, Postfach 2340, D-76125, Karlsruhe (Germany)
Description
The thermal conductivity of hyperstoichiometric SIMFUEL and UO2+x was obtained from thermal diffusivity, specific heat and density measurements. The thermal conductivity of UO2+x (no fission products present) decreases with increasing O/U ratio; a reduction of 15%, 37% and 56% at 600 C, and 11%, 23% and 33% at 1500 C, was found for O/U ratios of 2.007, 2.035 and 2.084, respectively. For 3 at% SIMFUEL there was little difference in the thermal conductivity of specimens annealed at oxygen potentials (ΔGO2) of -540 kJ/mol (corresponding to UO2.000) and -245 kJ/mol (corresponding to UO2.007). For SIMFUEL, annealed in reducing conditions, the fission products lowered the thermal conductivity significantly. However, for high oxygen potentials (ΔGO2≥-205 kJ/mol), the thermal conductivities of UO2+x and SIMFUEL were found to be approximately equal in the temperature range of 600 to 1500 C. Consequently, excess oxygen is the dominant factor contributing to thermal conductivity degradation at high oxygen potentials. ((orig.))
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 223
- Journal Issue
- 1
- Journal Page Range
- p. 51-60.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- Seminar on nuclear materials in conjunction with the 13. IUPAC conference on chemical thermodynamics.
- Dates
- 17-22 Jul 1994.
- Place
- Clermont-Ferrand (France).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 26054380
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; FISSION PRODUCTS; FUELS; OXYGEN; OXYGEN POTENTIAL; SPECIFIC HEAT; STOICHIOMETRY; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 1000-4000 K; THERMAL CONDUCTIVITY; THERMAL DEGRADATION; THERMAL DIFFUSIVITY; THERMAL FISSION; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; BARYON REACTIONS; CHALCOGENIDES; ELEMENTS; ENERGY; FISSION; FREE ENTHALPY; HADRON REACTIONS; HEAT TREATMENTS; ISOTOPES; MATERIALS; NEUTRON REACTIONS; NONMETALS; NUCLEAR REACTIONS; NUCLEON REACTIONS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; TEMPERATURE RANGE; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS