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U.S. Department of Energy
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Decontamination of HEPA filters

Conference ·
OSTI ID:6941815

Mound Facility, during many years of plutonium-238 experience, has recovered over 150 kg of plutonium-238. Much of this material was recovered from HEPA filters or from solid wastes such as sludge and slag. The objective of this task was to modify and improve the existing nitric acid leaching process used at Mound so that filters from the nuclear fuel cycle could be decontaminated effectively. Various leaching agents were tested to determine their capability for dissolving PuO/sub 2/, UO/sub 2/, U/sub 3/O/sub 8/, AmO/sub 2/, NpO/sub 2/, CmO/sub 2/, and ThO/sub 2/ in mixtures of the following: HNO/sub 3/-HF; HNO/sub 3/-HF-H/sub 2/SO/sub 4/; and HNO/sub 3/-(NH/sub 4/)/sub 2/Ce(NO/sub 3/)/sub 6/. Adsorption isotherms were obtained for two leaching systems. In some tests simulated contaminated HEPA filter material was used, while in others actual spent glovebox filters were used. The maximum decontamination factor of 833 was achieved in the recovery of plutonium-238 from actual filters. The dissolution was accomplished by using a six-stage process with 4N HNO/sub 3/-0.23M (NH/sub 4/)/sub 2/Ce(NO/sub 3/)/sub 6/ as the leaching agent. Thorium oxide was also effectively dissolved from filter media using a mixture of nitric acid and ceric ammonium nitrate. Sodium carbonate and Na/sub 2/CO/sub 3/-KNO/sub 3/ fusion tests were performed using simulated PuO/sub 2/-contaminated filter media at various temperatures. Approximately 70 wt% of the PuO/sub 2/ was soluble in a mixture composed of 70 wt% Na/sub 2/CO/sub 3/-30 wt% KNO/sub 3/ (heated for 1 h at 950/sup 0/C). 23 figs., 14 tables.

Research Organization:
Mound Facility, Miamisburg, OH (USA)
DOE Contract Number:
EY-76-C-04-0053
OSTI ID:
6941815
Report Number(s):
MLM-2537(OP); CONF-780819-1
Country of Publication:
United States
Language:
English