Zeolite vitrification demonstration program: characterization of radioactive vitrified zeolite materials

Technical Report · Sun Jan 01 00:00:00 EST 1984

DOI:https://doi.org/10.2172/5355684· OSTI ID:5355684

Barner, J O; Daniel, J L; Marshall, R K

The leach behavior of radioactive vitrified zeolite material was studied as part of the Three Mile Island (TMI) Zeolite Vitrification Program conducted by Pacific Northwest Laboratory (PNL). Experimental procedures, test results, and discussions of the results are presented. The leach behavior of material from three canisters of vitrified zeolite is discussed in terms of the normalized weight loss of the glass-formers and the normalized activity loss of the fission products cesium and strontium. The leach behavior of the radioactive vitrified zeolite material is also compared to the leach behavior of MCC 76-68 reference glass. The effects of changes in the surface microstructure of the vitrified zeolite that occurred during leaching are also presented. 3 references, 23 figures, 10 tables.

• Research Organization: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5355684
• Report Number(s): GEND-INF-043; ON: DE84007353
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BOROSILICATE GLASS
LEACHING
CESIUM
STRONTIUM
ZEOLITES
DISSOLUTION
EXPERIMENTAL DATA
HIGH-LEVEL RADIOACTIVE WASTES
LOW-LEVEL RADIOACTIVE WASTES
MICROSTRUCTURE
THREE MILE ISLAND-2 REACTOR
VITRIFICATION
ALKALI METALS
ALKALINE EARTH METALS
CRYSTAL STRUCTURE
DATA
ELEMENTS
ENRICHED URANIUM REACTORS
GLASS
INFORMATION
INORGANIC ION EXCHANGERS
ION EXCHANGE MATERIALS
MATERIALS
METALS
MINERALS
NUMERICAL DATA
POWER REACTORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTORS
SEPARATION PROCESSES
THERMAL REACTORS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
052001* - Nuclear Fuels- Waste Processing