Initial Series of Ruthenium Adsorption Optimization Studies

Technical Report · Wed Aug 01 00:00:00 EDT 2018

DOI:https://doi.org/10.2172/1479744· OSTI ID:1479744

Spencer, Barry B. ^[1]; Bruffey, Stephanie H. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

The processing of used nuclear fuel releases volatile and semivolatile radionuclides into the off-gas streams associated with the various processing steps. Ongoing efforts to develop methods to control the release of gaseous radionuclides to the environm ent have identified ruthenium (specifically ¹⁰⁶Ru) as one of the semivolatile nuclides requiring a high degree of abatement. The tritium pretreatment process will release a fraction of the ruthenium as volatile ruthenium tetroxide (RuO₄). Tests were conducted to examine the deposition phenomena and provide prelim inary information pertinent to an engineering design of a sorption bed to remove RuO₄ from a gas stream (e.g., approximate length of the mass transfer zone and the loading per unit mass of sorbent).

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1479744
• Report Number(s): ORNL/SPR-2018/913; NTRD-MRWFD-2018-tbd
• Country of Publication: United States
• Language: English

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS