Published May 1995 | Version v1
Journal article

Thermal conductivity of hyperstoichiometric SIMFUEL

  • 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).