245 Solvent Extraction and Adsorption in Spent Fuel Reprocessing and Radioactive Waste Management


Description:
This session will detail advances in the development of solvent extraction and adsorption technologies for the separation and recycle of radioactive material from spent nuclear fuel or treatment of radioactive waste. Additionally, contributions detailing the implementation of solvent extraction technologies for radioactive waste treatment or spent fuel re-processing are of interest.

Sponsor:
Nuclear Engineering Division


Chair:
Jack D. Law
Manager
Idaho National Laboratory
Aqueous Separation and Radiochemistry
PO Box 1625
Idaho Falls, ID
83415-3870
Fax Number: 208-526-2930
Email: jack.law@inl.gov

Co-Chair:
Kevin Lyon
Chemical Engineer
Idaho National Laboratory
Aqueous Separations and Radiochemistry
Idaho Falls, ID
Phone Number: 208-526-4455
Email: Kevin.Lyon@inl.gov


Papers:
245a
The Preparation of Titanate Nano-Materials Removing Efficiently Cs-137 from Radioactive Waste Water
Dejun LIU, State Power Investment Company Research Institute; Jing Fu, State Power Investment Company Research Institute; Rong Zhang, State Power Investment Company Research Institute; Ning Ma, State Power Investment Company Research Institute; Tian Luo, State Power Investment Company Research Institute
245b
Aging Processes of Ag-Exchanged Mordenite and Ag-Functionalized Silica Aerogel in Spent Nuclear Fuel Reprocessing Off Gases
Yue Nan, Syracuse University; Abney Carter, Oak Ridge National Laboratory; Seungrag Choi, Syracuse University; Jiuxu Liu, Syracuse University; Lawrence L. Tavlarides, Syracuse University
458e
Adsorption Models for Treatment of Nuclear Reprocessing Off-Gases
Austin Ladshaw, Georgia Institute of Technology; Sotira Yiacoumi, Georgia Institute of Technology; Yue Nan, Syracuse University; Lawrence L. Tavlarides, Syracuse University; Costas Tsouris, Oak Ridge National Laboratory
245d
Selective Adsorption for Kr/Xe Capture and Separation
Amy Welty, Idaho National Laboratory; Mitchell Greenhalgh, Idaho National Laboratory; Troy G. Garn, Idaho National Laboratory
Abstract Submissions Closed
See more of this Group/Topical: Nuclear Engineering Division - See also ICE
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