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Title: Laboratory studies in support of the West Valley sludge mobilization wash

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:7194760
; ; ; ;  [1]
  1. West Valley Nuclear Services Co., NY (United States)

The vitrification of the West Valley Demonstration Project (WVDP) high-level waste (HLW) requires the removal of substantial amounts of sulfate. The solubility of sulfate in the glass produced in the existing flow sheet using a slurry-fed ceramic melter is 0.3 wt%. Any sulfate above this level would form a molten salt layer on the surface of the melt. This layer would interfere with the melting process and result in an unacceptable borosilicate glass. The amount of sludge that could be put in the glass would be much less than planned, and the number of glass canisters necessary for solidifying the WVDP HLW would be substantially increased. Laboratory studies were recently performed to determine an acceptable flow sheet and operational parameters for the sulfate removal. Three technologies that meet the WVDP requirements were identified and tested in the laboratory to reduce the concentration of plutonium and uranium in the wash water. At this time, experimental results strongly indicate that the technologies can be implemented successfully at the WVDP. Current information also suggests that there should be no significant delay in solidifying the HLW as a result of using these methods.

OSTI ID:
7194760
Report Number(s):
CONF-920606-; CODEN: TANSA
Journal Information:
Transactions of the American Nuclear Society; (United States), Vol. 65; Conference: American Nuclear Society annual meeting, Boston, MA (United States), 7-12 Jun 1992; ISSN 0003-018X
Country of Publication:
United States
Language:
English