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Title: Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin

Abstract

When immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These solids are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new process to remove Cs from the caustic supernate. An organic ion exchange resin is used. This resin was then mixed with sludge andfrit and vitrified. Using an organic ion exchange resin rather than zeolite or the organic precipitant has certain advantages. Some of these are discussed in the paper. Results in the paper indicate that a mixture of the resin, sludge and frit can be successfully vitrified in a joule-heated, slurry fed melter. The redox state of the glass is lowered by the presence of the resin in the feed, but the glass is still suitable as a canistered wasteform for radioactive waste glass.

Authors:
; ; ;
Publication Date:
Research Org.:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10127169
Report Number(s):
WSRC-MS-91-465; CONF-921101-92
ON: DE93006873
DOE Contract Number:  
AC09-89SR18035
Resource Type:
Conference
Resource Relation:
Conference: 16. Materials Research Society (MRS) fall meeting,Boston, MA (United States),30 Nov - 5 Dec 1992; Other Information: PBD: [1991]
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; SLUDGES; CHEMICAL ANALYSIS; BOROSILICATE GLASS; HIGH-LEVEL RADIOACTIVE WASTES; VITRIFICATION; SAVANNAH RIVER PLANT; RADIOACTIVE WASTE PROCESSING; ORGANIC COMPOUNDS; ION EXCHANGE; CESIUM 137; ZEOLITES; MELTING; HYDROLYSIS; PH VALUE; RELIABILITY; REDOX REACTIONS; 052001; WASTE PROCESSING

Citation Formats

Bibler, N E, Bibler, J P, Andrews, M K, and Jantzen, C M. Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin. United States: N. p., 1991. Web.
Bibler, N E, Bibler, J P, Andrews, M K, & Jantzen, C M. Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin. United States.
Bibler, N E, Bibler, J P, Andrews, M K, and Jantzen, C M. Tue . "Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin". United States. https://www.osti.gov/servlets/purl/10127169.
@article{osti_10127169,
title = {Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin},
author = {Bibler, N E and Bibler, J P and Andrews, M K and Jantzen, C M},
abstractNote = {When immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These solids are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new process to remove Cs from the caustic supernate. An organic ion exchange resin is used. This resin was then mixed with sludge andfrit and vitrified. Using an organic ion exchange resin rather than zeolite or the organic precipitant has certain advantages. Some of these are discussed in the paper. Results in the paper indicate that a mixture of the resin, sludge and frit can be successfully vitrified in a joule-heated, slurry fed melter. The redox state of the glass is lowered by the presence of the resin in the feed, but the glass is still suitable as a canistered wasteform for radioactive waste glass.},
doi = {},
url = {https://www.osti.gov/biblio/10127169}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1991},
month = {12}
}

Conference:
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