RELEASE OF FISSION GASES FROM UO$sub 2$ DURING AND AFTER IRRADIATION
Technical Report
·
OSTI ID:4713957
Sintered UO/sub 2/ specimens with densities 82, 92, and 99% of theoretical were irradiated in a beam tube of the BRR, and the fission gases released during irradiation were collected for gamma-ray spectrometric determination of release rates for several fission-gas isotopes. In-pile and out- of-pile release at temperatures to 1650 un. Concent 85% C was studied. At 1000 to 1650 un. Concent 85% C the diffusion coefficients for Xe/sup 133/, Xe/sup 135/ , and Kr/sup 85m/ were expressed by the relation D = D/sub 0/ exp (-Q/RT), where D/sub 0/ =2.0 x 10/sup -3/ to 4.6 x 10/sup -3/ cm/su p 2/ per sec and Q = 87 to 92 kcal per mole. Below 1000 un. Concent 85% C, the in-pile gas release rates were relatively insensitive to changes in temperature, suggesting that diffusion was not occurring and that diffusion coefficients are of doubtful significance in describing gas release below about 1000 un. Concent 85% C under in-pile conditions. The experimental relation between gas release rate and the fission- gas half-life also suggest that below 1000 un. Concent 85% C diffusion was not the principal in-pile release mechanism. It was also observed that the release below 1000 un. Concent 85% C was not the result of only a simple recoil mechanism. The reasonable agreement between inpile and out-of-pile diffusion coefficients above 1000 un. Concent 85% C suggests that for low burnups accurate difiusion data can be obtained during postirradiation annealing out-of-pile. For specimen densities in the range of 92 to 99% of theoretical the equivalent-sphere model for expressing fuelsurface geometry led to consistent results in analysis of gas-release by volume diffusion. (auth)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-17-022216
- OSTI ID:
- 4713957
- Report Number(s):
- BMI-1623
- Country of Publication:
- United States
- Language:
- English
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