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Title: Process for vitrification of contaminated sodium oxide

Abstract

A glass composition was developed to accommodate 30 wt % sodium oxide and resist devitrification and leaching. An in-can melting process that is compatible with a comtaminated sodium calciner developed by Argonne National Laboratory was tested both on a laboratory and on an engineering scale and found to be viable. The Liquid Metal Fast Breeder Reactor experimental program continues to produce elemental sodium contaminated with radionuclides. This material is presently in temporary storage facilities because the current criterion will not permit alkali metals to be disposed of in shallow land burials. As a first step in treatment, Argonne National Laboratory (ANL) has developed a calciner that will convert the sodium metal to an oxide. In work supported by the U.S. Department of Energy, Pacific Northwest Laboratory (PNL) is developing and demonstrating a process that is compatible with the calciner and facilities at ANL-West for incorporating sodium oxide into a glass. Glass, which normally contains sodium oxide, was chosen as the waste form because it is chemically durable and nondispersible. It is simple to produce, and the technology for incorporating nuclear wastes into glass is well developed.

Authors:
;
Publication Date:
Research Org.:
Pacific Northwest Lab., Richland, WA (USA)
OSTI Identifier:
6285068
Report Number(s):
PNL-SA-10993; CONF-830451-7
ON: DE83011951
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Conference
Resource Relation:
Conference: American Ceramic Society annual meeting, Chicago, IL, USA, 25 Apr 1983
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; RADIOACTIVE WASTE PROCESSING; SOLIDIFICATION; SODIUM OXIDES; VITRIFICATION; GLASS; ALKALI METAL COMPOUNDS; CHALCOGENIDES; MANAGEMENT; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PROCESSING; SODIUM COMPOUNDS; WASTE MANAGEMENT; WASTE PROCESSING; 052001* - Nuclear Fuels- Waste Processing

Citation Formats

Blair, H.T., and Mellinger, G.B. Process for vitrification of contaminated sodium oxide. United States: N. p., 1983. Web.
Blair, H.T., & Mellinger, G.B. Process for vitrification of contaminated sodium oxide. United States.
Blair, H.T., and Mellinger, G.B. Tue . "Process for vitrification of contaminated sodium oxide". United States.
@article{osti_6285068,
title = {Process for vitrification of contaminated sodium oxide},
author = {Blair, H.T. and Mellinger, G.B.},
abstractNote = {A glass composition was developed to accommodate 30 wt % sodium oxide and resist devitrification and leaching. An in-can melting process that is compatible with a comtaminated sodium calciner developed by Argonne National Laboratory was tested both on a laboratory and on an engineering scale and found to be viable. The Liquid Metal Fast Breeder Reactor experimental program continues to produce elemental sodium contaminated with radionuclides. This material is presently in temporary storage facilities because the current criterion will not permit alkali metals to be disposed of in shallow land burials. As a first step in treatment, Argonne National Laboratory (ANL) has developed a calciner that will convert the sodium metal to an oxide. In work supported by the U.S. Department of Energy, Pacific Northwest Laboratory (PNL) is developing and demonstrating a process that is compatible with the calciner and facilities at ANL-West for incorporating sodium oxide into a glass. Glass, which normally contains sodium oxide, was chosen as the waste form because it is chemically durable and nondispersible. It is simple to produce, and the technology for incorporating nuclear wastes into glass is well developed.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1983},
month = {3}
}

Conference:
Other availability
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