Ion exchange of fission products between zeolite and a molten salt

Light Metals: Proceedings of Sessions, TMS Annual Meeting (Warrendale, Pennsylvania)

Volumn , Issue , 2002, Pages 37-43

  Gougar, Mary Lou D ^a   Simpson, Michael F ^a   Battisti, Terry J ^a   Scheetz, Barry E ^a  

^a ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CERAMIC WASTE FORM; MICROPORES; MOLTEN CHLORIDE SALT SOLUTION;

ELECTROMETALLURGY; FISSION PRODUCTS; MATHEMATICAL MODELS; MOLTEN MATERIALS; RADIOACTIVITY; SODIUM CHLORIDE; SPENT FUELS; ZEOLITES;

ION EXCHANGE;

EID: 0036241307     PISSN: 10969586     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. Spent fuel treatment and mineral waste form development at Argonne National Laboratory-West
2. Characteristics of Department of Energy spent nuclear fuel
3. Occlusion and ion exchange in the molten (lithium chloride-potassium chloride-alkali metal) salt + zeolite 4A system with alkali metal chlorides of sodium, rubidium, and cesium