skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Minor component study for simulated high-level nuclear waste glasses (Draft)

Abstract

Hanford Site single-shell tank (SSI) and double-shell tank (DSI) wastes are planned to be separated into low activity (or low-level waste, LLW) and high activity (or high-level waste, HLW) fractions, and to be vitrified for disposal. Formulation of HLW glass must comply with glass processibility and durability requirements, including constraints on melt viscosity, electrical conductivity, liquidus temperature, tendency for phase segregation on the molten glass surface, and chemical durability of the final waste form. A wide variety of HLW compositions are expected to be vitrified. In addition these wastes will likely vary in composition from current estimates. High concentrations of certain troublesome components, such as sulfate, phosphate, and chrome, raise concerns about their potential hinderance to the waste vitrification process. For example, phosphate segregation in the cold cap (the layer of feed on top of the glass melt) in a Joule-heated melter may inhibit the melting process (Bunnell, 1988). This has been reported during a pilot-scale ceramic melter run, PSCM-19, (Perez, 1985). Molten salt segregation of either sulfate or chromate is also hazardous to the waste vitrification process. Excessive (Cr, Fe, Mn, Ni) spinel crystal formation in molten glass can also be detrimental to melter operation.

Authors:
; ; ; ; ;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
207560
Report Number(s):
PNNL-10996; PVTD-T3C-95-125
ON: DE96008249; TRN: 96:009491
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Feb 1996
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; HIGH-LEVEL RADIOACTIVE WASTES; VITRIFICATION; MATHEMATICAL MODELS; CERAMIC MELTERS; BOROSILICATE GLASS; SULFATES; CRYSTALLIZATION; VISCOSITY; CHEMICAL COMPOSITION

Citation Formats

Li, H, Langowskim, M H, Hrma, P R, Schweiger, M J, Vienna, J D, and Smith, D E. Minor component study for simulated high-level nuclear waste glasses (Draft). United States: N. p., 1996. Web. doi:10.2172/207560.
Li, H, Langowskim, M H, Hrma, P R, Schweiger, M J, Vienna, J D, & Smith, D E. Minor component study for simulated high-level nuclear waste glasses (Draft). United States. https://doi.org/10.2172/207560
Li, H, Langowskim, M H, Hrma, P R, Schweiger, M J, Vienna, J D, and Smith, D E. 1996. "Minor component study for simulated high-level nuclear waste glasses (Draft)". United States. https://doi.org/10.2172/207560. https://www.osti.gov/servlets/purl/207560.
@article{osti_207560,
title = {Minor component study for simulated high-level nuclear waste glasses (Draft)},
author = {Li, H and Langowskim, M H and Hrma, P R and Schweiger, M J and Vienna, J D and Smith, D E},
abstractNote = {Hanford Site single-shell tank (SSI) and double-shell tank (DSI) wastes are planned to be separated into low activity (or low-level waste, LLW) and high activity (or high-level waste, HLW) fractions, and to be vitrified for disposal. Formulation of HLW glass must comply with glass processibility and durability requirements, including constraints on melt viscosity, electrical conductivity, liquidus temperature, tendency for phase segregation on the molten glass surface, and chemical durability of the final waste form. A wide variety of HLW compositions are expected to be vitrified. In addition these wastes will likely vary in composition from current estimates. High concentrations of certain troublesome components, such as sulfate, phosphate, and chrome, raise concerns about their potential hinderance to the waste vitrification process. For example, phosphate segregation in the cold cap (the layer of feed on top of the glass melt) in a Joule-heated melter may inhibit the melting process (Bunnell, 1988). This has been reported during a pilot-scale ceramic melter run, PSCM-19, (Perez, 1985). Molten salt segregation of either sulfate or chromate is also hazardous to the waste vitrification process. Excessive (Cr, Fe, Mn, Ni) spinel crystal formation in molten glass can also be detrimental to melter operation.},
doi = {10.2172/207560},
url = {https://www.osti.gov/biblio/207560}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Feb 01 00:00:00 EST 1996},
month = {Thu Feb 01 00:00:00 EST 1996}
}