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- W54871296 abstract "Effluents released to the off gas during the in situ vitrification (ISV) of a test site have been characterized by Pacific Northwest Laboratory. The site consisted of a 19 L waste package of soil containing 600 nCi/g transuranic and 30,000 nCi/g mixed fission products surrounded by uncontaminated soil. Radioactive isotopes present in the package were /sup 241/Am, /sup 238///sup 239/Pu, /sup 137/Cs, /sup 106/Ru, /sup 90/Sr, and /sup 60/Co. The ISV process melted the waste package and surrounding soil and immobilized the radionuclides in place, producing a durable, 8.6 metric ton glass and crystalline monolith. The test successfully demonstrated that the process provides containment of radioactive material. No release to the environment was detected during processing of cooldown. Due to the high temperature during processing, some gases were released into the off-gas hood that was over the test site. The hood was maintained at a slight negative pressure to contain any volatile or entrained material during processing. Gases passed from the hood to an off-gas treatment system where they were treated using a venturi-ejector scrubber, a tandem nozzle gas cleaner scrubber followed by a condenser, heater, and two stages of HEPA filters. The off-gas treatment system is located in themore » semi-trailer to allow transport of the process to other potential test sites. Retention of all radionuclides by the vitrified zone was greater than 99%. Soil-to-off-gas decontamination factors (DFs) for transuranic elements averaged greater than 4000 and for fission products, DFs ranged from 130 for /sup 137/Cs to 3100 for /sup 90/Sr. 7 references, 15 figures, 4 tables.« less" @default.
- W54871296 created "2016-06-24" @default.
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- W54871296 date "1984-08-01" @default.
- W54871296 modified "2023-09-27" @default.
- W54871296 title "Off-gas treatment and characterization for a radioactive in situ vitrification test" @default.
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