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Title: FISSION-PRODUCT RELEASE FROM (Th,U)C$sub 2$-GRAPHITE FUELS

Technical Report ·
OSTI ID:4728980

Xe retention at first, but degradation occurred as high fuel burnup was achieved. Ba was found to permeate pyrolytic C coatings which were impermeable to Xe, particularly at temperatures above 1400 deg C. Retention of I/sub 2/ and Te by C coatings, although not quite as good as Xe retention, was much better than I/sub 2/ and Te retention by uncoated (Th,U)C/sub 2/ particles. In postirradiation annealing runs, the rate of release of Xe/sup 133/ from coated and uncoated (Th,U)C/sub 2/ fuels was measured at 1000 to 1700 deg C. The release of Ba/sup 14-/, Te/sup 131/, and I/sup 131/ was also determined for lightly irradiated samples. Xe/sup 133/ release was interpreted in terms of the equivalent spheres'' approach. Release rates for shorthalf-life Xe predicted by this treatment are in approximate agreement with steady-state Xe/sup 138/ and Xe/ sup 139/ release rates obtained out-of-pile for uncoated (Th,U)C/sub 2/ particles by using an electron linear accelerator to produce a steady rate of photofissions. Data for Kr/sup 85m/, Kr/sup 87/, Kr/sup 88/, and Kr/sup were also obtained in these out-of-pile experiments. Inpile experiments on samples of coated particles were performed to determine the effects of high fuel burnup and temperature on the retention of Kr and Xe fission-product nuclides. Activation energies for release were found to be about 29 kcal/mole for Kr and 39 kcal/mole for Xe. (auth)

Research Organization:
General Atomic Div. General Dynamics Corp., San Diego, Calif.
DOE Contract Number:
AT(04-3)-314
NSA Number:
NSA-17-014889
OSTI ID:
4728980
Report Number(s):
GA-3599
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English