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Hot cell studies of tritium removal from and dissolution of an irradiated thoria fuel

Conference ·
OSTI ID:5120516
Tritium removal and dissolution studies on an irradiated thoria-based fuel were conducted in the High Level Caves at the Savannah River Laboratory (SRL). The objectives of these studies were to define the effects of key process-related parameters on tritium evolution and subsequent dissolution. The test program at SRL determined the effects on tritium removal of particle size, heating temperature, oxidation, and agitation. ThO/sub 2//UO/sub 2/ (95%/5%) fuel from the Elk River Reactor, irradiated to about 12,000 MWD/MTHM and cooled for about 12 years, was used in the tests. The thoria/urania fuel pellets were separated from the stainless steel cladding and were divided into size fractions to determine the particle-size distribution resulting from the decladding process. In the tritium removal tests, the effect of heating several different particle-size fractions was studied at temperatures ranging from 600 to 1000/sup 0/C in the presence of air for 10 to 30 hours. Each of the roasted samples (about 100 grams) was subsequently dissolved in refluxing Thorex reagent (13M HNO/sub 3/, 0.05M HF, and 0.1M Al(NO/sub 3/)/sub 3/) to determine the residual tritium. The amount of insoluble residue remaining after the dissolution was determined and characterized.
Research Organization:
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
DOE Contract Number:
AC09-76SR00001
OSTI ID:
5120516
Report Number(s):
DP-MS-80-11; CONF-800943-8
Country of Publication:
United States
Language:
English