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Title: Corrosion textures of simulated nuclear waste glass and nuclear waste slag when exposed to water vapor hydration at 200 C

Conference ·
OSTI ID:491032
;  [1]
  1. Montana Coll. of Mineral Science and Technology, Butte, MT (United States). Chemistry and Geochemistry Dept.

A Savannah River Laboratory nuclear waste glass (SRL) and a plasma furnace nuclear waste slag were subjected to vapor hydration as small suspended rectangular samples within a sealed reaction bomb at 200 C for time periods of up to 26 days. The samples were then removed from the reaction bomb and the residual water analyzed by ICP and ICP-MS for trace elements and bulk glass constituents. The sample hydration rind thickness was measured and photographed with an optical microscope and the data plotted as thickness vs. time profiles which are presented as an indicator of the relative durability of the waste medium. The chemical transport of various dissolved glass constituents from the bulk medium to the sample surface developed residual diffusion textures within the hydration rind which have been investigated relative to the residual bomb water chemistry and SEM-EDX analysis of the hydration rind. These textures reveal that the water vapor diffuses into the surface of the nuclear waste slag along the path of least resistance and selectively dissolves the more soluble constituents within the slag. The development of secondary silicate phases and selective dissolution of soluble elements contribute to extensive fracturing of the hydrated region.

OSTI ID:
491032
Report Number(s):
CONF-9406250-; TRN: 97:011832
Resource Relation:
Conference: 9. Annual conference on hazardous waste remediation, Bozeman, MT (United States), 8-10 Jun 1994; Other Information: PBD: 1994; Related Information: Is Part Of Proceedings of the 9. annual conference on hazardous waste remediation; Erickson, L.E.; Tillison, D.L.; Grant, S.C.; McDonald, J.P. [eds.]; PB: 389 p.
Country of Publication:
United States
Language:
English