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In-pile thermal conductivity of selected ThO/sub 2/--UO/sub 2/ fuels at low depletions (LWBR Development Program)

Technical Report ·
OSTI ID:6757275
The in-pile thermal conductivities of selected ThO/sub 2/-UO/sub 2/, fuel materials were determined by direct measurement using an in-pile extension of the radial heat-flow technique. The tests incorporated ThO/sub 2/ + 3.1 wt % UO/sub 2/, ThO/sub 2/ + 7.7 wt % UO/sub 2/, ThO/sub 2/ + 10 wt % UO/sub 2/ and UO/sub 2/ specimens. The microstructure, stoichiometry, density, impurity content, and unirradiated thermal conductivity were determined for each fuel material. The test results showed no statistically significant differences between the in-pile and unirradiated thermal conductivities for steady-state operation for the UO/sub 2/ specimens at 600 < or = T < or = 1000/sup 0/C, at a burnup of up to 5.6 x 10/sup 18/ fission/cm/sup 3/ and for the ThO/sub 2/-UO/sub 2/ specimens at 400 < or = T < or = 1000/sup 0/C at a burnup of up to 1.4 x 10/sup 19/ fission/cm/sup 3/. The in-pile conductivities were slightly, but significantly, greater than the unirradiated conductivities at 1000 < T < or = 1300/sup 0/C for the UO/sub 2/ specimens and at 1000 < T < or = 1700/sup 0/C for the ThO/sub 2/-UO/sub 2/ specimens. However, this is considered to be an experimental anomaly and is not taken as a meaningful enhancement of in-pile conductivity. The maximum depletions achieved in these tests are one to two orders of magnitude less than typical in-service depletions. Hence, the test results do not reflect any possible changes in conductivity by the accumulation of fission products and the formation of fission gas bubbles. (NSA 23: 36271)
Research Organization:
Bettis Atomic Power Lab., Pittsburgh, PA (USA)
DOE Contract Number:
AT(11-1)-GEN-14
OSTI ID:
6757275
Report Number(s):
WAPD-TM-758
Country of Publication:
United States
Language:
English