Iron Phosphate Glasses: An Alternative for Vitrifying Certain Nuclear Wastes
Author(s) -
Delbert E. Day,
Chandra S. Ray,
Cheol-Woon Kim
Publication year - 2004
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/835729
Subject(s) - vitrification , borosilicate glass , radioactive waste , waste management , high level waste , savannah river site , materials science , volume (thermodynamics) , phosphate glass , waste treatment , waste disposal , environmental science , radiochemistry , chemistry , metallurgy , engineering , medicine , physics , optoelectronics , doping , quantum mechanics , andrology
Vitrification of nuclear waste in a glass is currently the preferred process for waste disposal. DOE currently approves only borosilicate (BS) type glasses for such purposes. However, many nuclear wastes, presently awaiting disposal, have complex and diverse chemical compositions, and often contain components that are poorly soluble or chemically incompatible in BS glasses. Such problematic wastes can be pre-processed and/or diluted to compensate for their incompatibility with a BS glass matrix, but both of these solutions increases the wasteform volume and the overall cost for vitrification. Direct vitrification using alternative glasses that utilize the major components already present in the waste is preferable, since it avoids pre-treating or diluting the waste, and, thus, minimizes the wasteform volume and overall cost
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