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Title: Initial demonstration of DWPF process and product control strategy using actual radioactive waste

Abstract

The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150{degrees}C. Process control and product quality are ensured by proper control of the melter feed composition. Algorithms have been developed to predict the processability of the melt and the durability of the final glass based on this feed composition. To test these algorithms, an actual radioactive waste contained in a shielded facility at SRS was analyzed and a frit composition formulated using a simple computer spreadsheet which contained the algorithms. This frit was then mixed with the waste and the resulting slurry fed to a research scale joule-heated melter operated remotely. Approximately 24 kg of glass were successfully prepared. This paper will describe the frit formulation, the vitrification process, and the glass durability.

Authors:
; ; ;
Publication Date:
Research Org.:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10129438
Report Number(s):
WSRC-MS-91-012; CONF-910430-23
ON: DE92009635
DOE Contract Number:  
AC09-89SR18035
Resource Type:
Conference
Resource Relation:
Conference: 93. annual meeting and exposition of the American Ceramic Society (ACerS),Cincinnati, OH (United States),28 Apr - 2 May 1991; Other Information: PBD: [1991]
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; HIGH-LEVEL RADIOACTIVE WASTES; VITRIFICATION; DEMONSTRATION PROGRAMS; SAVANNAH RIVER PLANT; CERAMIC MELTERS; PROCESS CONTROL; BOROSILICATE GLASS; ALGORITHMS; RADIOACTIVE WASTE PROCESSING; SOLIDIFICATION; 052001; WASTE PROCESSING

Citation Formats

Andrews, M K, Bibler, N E, Jantzen, C M, and Beam, D C. Initial demonstration of DWPF process and product control strategy using actual radioactive waste. United States: N. p., 1991. Web.
Andrews, M K, Bibler, N E, Jantzen, C M, & Beam, D C. Initial demonstration of DWPF process and product control strategy using actual radioactive waste. United States.
Andrews, M K, Bibler, N E, Jantzen, C M, and Beam, D C. 1991. "Initial demonstration of DWPF process and product control strategy using actual radioactive waste". United States. https://www.osti.gov/servlets/purl/10129438.
@article{osti_10129438,
title = {Initial demonstration of DWPF process and product control strategy using actual radioactive waste},
author = {Andrews, M K and Bibler, N E and Jantzen, C M and Beam, D C},
abstractNote = {The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150{degrees}C. Process control and product quality are ensured by proper control of the melter feed composition. Algorithms have been developed to predict the processability of the melt and the durability of the final glass based on this feed composition. To test these algorithms, an actual radioactive waste contained in a shielded facility at SRS was analyzed and a frit composition formulated using a simple computer spreadsheet which contained the algorithms. This frit was then mixed with the waste and the resulting slurry fed to a research scale joule-heated melter operated remotely. Approximately 24 kg of glass were successfully prepared. This paper will describe the frit formulation, the vitrification process, and the glass durability.},
doi = {},
url = {https://www.osti.gov/biblio/10129438}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Dec 31 00:00:00 EST 1991},
month = {Tue Dec 31 00:00:00 EST 1991}
}

Conference:
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