THERMAL CONDUCTIVITY DETERMINATIONS ON URANIUM DIOXIDE BY A RADIAL FLOW METHOD
Technical Report
·
OSTI ID:4032516
Thermal conductivities in the temperature range 100 to 1500 deg C were determined by a radial flow method for five specimens of uranium dioxide of 95% theoretical density and made by different production routes. The temperature variation of conductivity of nominally stoichiometric UO/sub 2/ can be expressed in the form of thermal conductivity k = l/(A + 0.084 T ( deg K)) (cal cm/sup -1/ sec/sup -1/ deg C/sup -1/). where A is a constant for each material and dependent on the method of production. A has a value of 12 for material produced by the high-temperature route and for cold-compacted powder directly sintered in cracked ammonia at 1700 deg C. A lies between 30 and 36 for material produced by the low- temperature route and for cold-compacted non-stoichiometric powder sintered in argon at 1400 deg C for 2 hr and reduced in hydrogen at 1400 deg C for 2 hr. The dependence of the constant A on UO/sub 2/ structure is discussed. The factors considered most likely to contribute to the value of A are slight departures from stoichiometric composition, microcracking in specimens, and factors dependent on production methods. (auth)
- Research Organization:
- United Kingdom Atomic Energy Authority. Industrial Group. Culcheth Labs., Culcheth, Lancs, England
- NSA Number:
- NSA-15-016179
- OSTI ID:
- 4032516
- Report Number(s):
- IG-Report-51; NPCC-FEWP/P.700
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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