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Measurement of radioactive gaseous effluents from voloxidation and dissolution of spent nuclear fuel

Conference ·
OSTI ID:6942198
Laboratory-scale tests gave data on the release of tritium, /sup 14/C, /sup 85/Kr, and /sup 129/I as radioactive gases from spent nuclear fuels during voloxidation and dissolution. Voloxidation, a proposed reprocessing step, is intended to remove tritium from fuel by oxidation of UO/sub 2/ to U/sub 3/O/sub 8/ prior to dissolution of the fuel with nitric acid. /sup 14/C, /sup 85/Kr, and /sup 129/I may be evolved in both steps. Quantitative data from the tests may be used in designing off-gas treatment processes and equipment. The tests were performed in a shielded cell with a combination voloxidizer-dissolver. With a recirculating off-gas system, tritium and /sup 14/C were trapped on molecular sieves; /sup 129/I was trapped on silver-exchanged zeolite. /sup 85/Kr was measured by online gamma-ray counting. Zircaloy-clad UO/sub 2/ fuels from H. B. Robinson-2, Oconee-1, and Saxton reactors, with burnups from approximately 100 to approximately 28,000 MWD/MTHM, were tested. The results confirm that voloxidation released most of the tritium but only small fractions of the /sup 14/C, /sup 85/Kr, and /sup 129/I; the remainder of these radioactive gases evolved when the voloxidized fuels were dissolved. Voloxidation off-gases typically contained >99.8% of the tritium, 17 to 22% of the /sup 14/C, 7 to 17% of the /sup 85/Kr, and <8% of the /sup 129/I. Tritium evolved as HTO, with <0.1% as HT.
Research Organization:
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
DOE Contract Number:
EY-76-C-09-0001
OSTI ID:
6942198
Report Number(s):
DP-MS-78-7; CONF-780819-21
Country of Publication:
United States
Language:
English