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U.S. Department of Energy
Office of Scientific and Technical Information

Vitrification in the presence of molten salts

Conference ·
OSTI ID:39197
; ;  [1]
  1. Westinghouse Savannah River Co., Aiken, SC (United States)

Glass is an advantageous material for the immobilization of nuclear wastes because of the simplicity of processing and its unique ability to accept a wide variety of waste elements into its network structure. Unfortunately, some anionic species which are present in the nuclear waste streams have only limited solubility in oxide glasses. This can result in either vitrification concerns or it can affect the integrity of the final vitrified waste form. The presence of immiscible salts can also corrode metals and refractories in the vitrification unit as well as degrade components in the off-gas system. The presence of a molten salt layer on the melt may alter the batch melting rate and increase operational safety concerns. These safety concerns relate to the interaction of the molten salt and the melter cooling fluids. Some preliminary data from ongoing experimental efforts examining the solubility of molten salts in glasses and the interaction of salts with melter component materials is included.

DOE Contract Number:
AC09-89SR18035
OSTI ID:
39197
Report Number(s):
CONF-940416--
Country of Publication:
United States
Language:
English