Zeolite vitrification demonstration program: characterization of radioactive vitrified zeolite materials
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A05/MF A01 as DE84007353.
Files
Additional details
Publishing Information
- Imprint Pagination
- 80 p.
- Report number
- GEND-INF--043
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15053817
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BOROSILICATE GLASS; CESIUM; DISSOLUTION; EXPERIMENTAL DATA; HIGH-LEVEL RADIOACTIVE WASTES; LEACHING; LOW-LEVEL RADIOACTIVE WASTES; MICROSTRUCTURE; STRONTIUM; THREE MILE ISLAND-2 REACTOR; VITRIFICATION; ZEOLITES
- Descriptors DEC
- 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; SILICATE MINERALS; THERMAL REACTORS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS