Published January 1984 | Version v1
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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.

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Additional details

Publishing Information

Imprint Pagination
80 p.
Report number
GEND-INF--043