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Title: Evaluation of glass as a matrix for solidifying Savannah River Plant waste: properties of glasses containing Li/sub 2/O

Abstract

Properties of waste forms made of borosilicate glass containing Li/sub 2/O combined with both simulated and actual Savannah River Plant (SRP) waste sludges were studied. The glass former, Frit 21, is presently the leading candidate for vitrifying SRP waste in a proposed process for long-term waste management. Devitrification of waste forms was inhibited by sludge components uranium and nickel, but was promoted by aluminum. Devitrification increased the leach rate of waste forms containing simulated sludges up to a factor of 20 in high-temperature leach tests and could be qualitatively correlated with the leach rate of waste forms containing actual sludges in room temperature tests. Room temperature leach rates were diffusion controlled throughout a 100-day test. Although sulfate solubility in Frit 21-sludge melts could be raised from 1 wt % to 2.5 wt % by slight modifications of the frit, this should not be necessary since Na/sub 2/SO/sub 4/ washes from actual sludges to levels below 0.5 wt %. It was demonstrated that waste forms can be dissolved in boiling 5M HNO/sub 3/ if waste recovery becomes necessary. 13 figures, 12 tables.

Authors:
;
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
OSTI Identifier:
6190422
Report Number(s):
DP-1498
TRN: 79-010261
DOE Contract Number:  
EY-76-C-09-0001
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; RADIOACTIVE WASTE PROCESSING; SOLIDIFICATION; RADIOACTIVE WASTES; DISSOLUTION; LEACHING; BOROSILICATES; CESIUM 137; CHEMICAL COMPOSITION; EXPERIMENTAL DATA; GLASS; ISOLATED VALUES; PLUTONIUM; SAVANNAH RIVER PLANT; SLUDGES; STRONTIUM 90; VITRIFICATION; ACTINIDES; ALKALI METAL ISOTOPES; ALKALINE EARTH ISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BORON COMPOUNDS; CESIUM ISOTOPES; DATA; DATA FORMS; ELEMENTS; EVEN-EVEN NUCLEI; INFORMATION; INTERMEDIATE MASS NUCLEI; ISOTOPES; MANAGEMENT; METALS; NATIONAL ORGANIZATIONS; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; PHASE TRANSFORMATIONS; PROCESSING; RADIOACTIVE MATERIALS; RADIOISOTOPES; SEPARATION PROCESSES; SILICON COMPOUNDS; STRONTIUM ISOTOPES; TRANSURANIUM ELEMENTS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES; 052001* - Nuclear Fuels- Waste Processing

Citation Formats

Plodinec, M.J., and Wiley, J.R. Evaluation of glass as a matrix for solidifying Savannah River Plant waste: properties of glasses containing Li/sub 2/O. United States: N. p., 1979. Web. doi:10.2172/6190422.
Plodinec, M.J., & Wiley, J.R. Evaluation of glass as a matrix for solidifying Savannah River Plant waste: properties of glasses containing Li/sub 2/O. United States. doi:10.2172/6190422.
Plodinec, M.J., and Wiley, J.R. Thu . "Evaluation of glass as a matrix for solidifying Savannah River Plant waste: properties of glasses containing Li/sub 2/O". United States. doi:10.2172/6190422. https://www.osti.gov/servlets/purl/6190422.
@article{osti_6190422,
title = {Evaluation of glass as a matrix for solidifying Savannah River Plant waste: properties of glasses containing Li/sub 2/O},
author = {Plodinec, M.J. and Wiley, J.R.},
abstractNote = {Properties of waste forms made of borosilicate glass containing Li/sub 2/O combined with both simulated and actual Savannah River Plant (SRP) waste sludges were studied. The glass former, Frit 21, is presently the leading candidate for vitrifying SRP waste in a proposed process for long-term waste management. Devitrification of waste forms was inhibited by sludge components uranium and nickel, but was promoted by aluminum. Devitrification increased the leach rate of waste forms containing simulated sludges up to a factor of 20 in high-temperature leach tests and could be qualitatively correlated with the leach rate of waste forms containing actual sludges in room temperature tests. Room temperature leach rates were diffusion controlled throughout a 100-day test. Although sulfate solubility in Frit 21-sludge melts could be raised from 1 wt % to 2.5 wt % by slight modifications of the frit, this should not be necessary since Na/sub 2/SO/sub 4/ washes from actual sludges to levels below 0.5 wt %. It was demonstrated that waste forms can be dissolved in boiling 5M HNO/sub 3/ if waste recovery becomes necessary. 13 figures, 12 tables.},
doi = {10.2172/6190422},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {2}
}

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