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Topic Title: ABSTRACT: Vitrification of High Chrome Oxide Nuclear Waste in Iron Phosphate Glasses
Topic Summary: W. Huang, et. al., Journal of Nuclear Materials. Examination of chemical durability
Created On: 5/22/2007 9:48 AM

 5/22/2007 9:48 AM

Lynne Robinson

Posts: 701
Joined: 2/3/2007

A simulated high level waste (HLW) containing 4 mass% chrome oxide, whose overall composition is representative of the high chrome oxide wastes at Hanford WA USA, was easily vitrified in a phosphate glass at temperatures ranging from 1150 °C, for waste loadings of 55 mass%, to 1250 °C for waste loadings of 75 mass%.

The link provided leads to the abstract only. The full article is available for sale from Elsevier.

Citation: Huang, W., Day, D.E., Chandra S.R,, Kim, C.-W., and Mogus-Milankovic, A. "Vitrification of High Chrome Oxide Nuclear Waste in Iron Phosphate Glasses." Journal of Nuclear Materials. 327(1) (April 2004): 46-57.

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