Glass Durability Along the Compositional Continuum Between a Phase Separated Frit and a Homogeneous Glass

Glass Durability Along the Compositional Continuum Between a Phase Separated Frit and a Homogeneous Glass

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Published: 1999

Total Pages: 5

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Seven non-radioactive glass compositions spanning the range of wastes to be processed in the Defense Waste Processing Facility (DWPF) were studied prior to start up of the Processing DWPF melter. These glasses were produced by Corning Glass Works and were designated Waste Compliance Plan (WCP) glasses. New glasses were melted by adding Frit 202 to the WCP-Purex glass and the resulting glass compositions were examined for amorphous phase separation using Transmission Electron Microscopy (TEM). The durability of the glasses was measured using the Product Consistency Test (PCT), ASTM C 1285-94.


Glass Durability Along the Compositional Continuum Between a Phase Separated Frit and a Homogenous Glass

Glass Durability Along the Compositional Continuum Between a Phase Separated Frit and a Homogenous Glass

Author:

Publisher:

Published: 1999

Total Pages:

ISBN-13:

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Seven non-radioactive glass compositions spanning the range of wastes to be processed in the Defense Waste Processing Facility (DWPF) were studied prior to start up of the Processing DWPF melter. These glasses were produced by Corning Glass Works and were designated Waste Compliance Plan (WCP) glasses. New glasses were melted by adding Frit 202 to the WCP-Purex glass and the resulting glass compositions were examined for amorphous phase separation using Transmission Electron Microscopy (TEM). The durability of the glasses was measured using the Product Consistency Test (PCT), ASTM C 1285-94.


Phase Stability Determinations of DWPF Waste Glasses. [Defense Waste Processing Facility].

Phase Stability Determinations of DWPF Waste Glasses. [Defense Waste Processing Facility].

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Published: 1992

Total Pages: 4

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The high-level radioactive wastes stored at Savannah River, will be immobilized in borosilicate glass in the Defense Waste Processing Facility (DWPF). Waste Acceptance Preliminary Specifications require that time-temperature-transformation (TTT) curves be provided for expected DWPF compositions, in order to predict the durability of the waste form. In order to derive these TTT curves, samples of simulated glasses are being heat treated and then analyzed. The seven simulated glasses include blend, high aluminum (HM) and high iron (Purex). X-ray diffraction show minimal crystallization for the heat treatments at 400, 1000 and 1100 C; 600 and 700 C produce the greatest amount of crystallization. Scanning electron microscopy show heterogeneous crystallization with the spinel forming on melt insolubles and the acmite nucleating on the spinel. Initial leaching results show that the glass durability decreases with increasing crystallinity for the 700 C glasses. Future plans are outlined. 2 tables, 9 refs. (DLC).


Production and Remediation of Low-sludge, Simulated Purex Waste Glasses, 1

Production and Remediation of Low-sludge, Simulated Purex Waste Glasses, 1

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Published: 1993

Total Pages: 17

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Glass produced during the Purex 4 campaigns of the Integrated Defense Waste Processing Facility (DWPF) Melter System (IDMS) and the 774 Research Melter contained a lower fraction of sludge components than targeted by the Product Composition Control System (PCCS). Purex 4 glass was more durable than the benchmark (EA) glass, but less durable than most simulated SRS high-level waste glasses. Also, Purex 4 glass was considerably less durable than predicted by the algorithm which will be used to control production of DWPF glass. A melter run was performed using the 774 Research Melter to determine if the initial PCCS target composition determined for Purex 4 would produce acceptable glass whose durability could be accurately modeled by Hydration Thermodynamics. Reagent grade oxides and carbonates were added to Purex 4 melter feed stock to simulate a higher sludge loading. Each canister of glass produced was sampled and the composition, crystallinity, and durability was determined. This document details the melter operation and composition and crystallinity analyses.


Performing a Chemical Durability Test on Radioactive High-level Nuclear Waste Glass

Performing a Chemical Durability Test on Radioactive High-level Nuclear Waste Glass

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Published: 1990

Total Pages: 31

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Savannah River Site (SRS), currently is storing (approximately)30 million gallons of highly radioactive nuclear wastes. The Defense Waste Processing Facility (DWPF) nearing completion at SRS will incorporate the radionuclides in these wastes into solid borosilicate glass for final disposal in a geologic repository. Because of the variability of the wastes in the tanks, borosilicate glasses of different compositions will be produced by the DWPF during the 20--25 years required to solidify all the wastes at SRS. A chemical durability test, the Product Consistency Test (PCT), has been developed at SRS to measure the consistency of the durability of these glasses. This paper describes the remote and hands-on procedures for performing the PCT on these radioactive glasses. Results will be presented that indicate the good precision of the PCT and indicate some of the chemistry involved in leaching radioactive elements from the glass. 9 refs., 1 fig., 4 tabs.


The Effect of Adding Crystalline Silicotitanate on the Durability, Liquidus, and Viscosity of Simulated High-level Waste Glasses at Savannah River Site

The Effect of Adding Crystalline Silicotitanate on the Durability, Liquidus, and Viscosity of Simulated High-level Waste Glasses at Savannah River Site

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Published: 2000

Total Pages: 5

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This report provides a summary of the results obtained for a limited variability study for glasses containing Crystalline Silicotitanate (CST), Monosodium Titanate (MST), and either simulated Purex or HM sludge. Twenty-two glasses containing Purex sludge and three glasses containing HM sludge were fabricated and tested. The fabricated glasses were tested for durability using the 7-day Product Consistency Test (PCT) and characterized by measuring the viscosity at 1,150 C and by determining an approximate, bounding liquidus temperature. The current models used by Defense Waste Processing Facility (DWPF) for predicting durability, viscosity, and liquidus temperature were applied to all 25 glasses. The goal of this work was to identify any major problems from a glass perspective, within the scope of this effort, which could potentially preclude the use of CST at DWPF.


Production and Remediation of Low Sludge Simulated Purex Waste Glasses, 2

Production and Remediation of Low Sludge Simulated Purex Waste Glasses, 2

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Published: 1993

Total Pages: 13

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Glass produced during the Purex 4 campaigns of the Integrated DWPF Melter System (IDMS) and the 774 Research Melter contained a lower fraction of sludge components than targeted by the Product Composition Control System (PCCS). Purex 4 glass was more durable than the benchmark (EA) glass, but was less durable than most other simulated SRS high-level waste glasses. Further, the measured durability of Purex 4 glass was not as well correlated with the durability predicted from the DWPF process control algorithm, probably because the algorithm was developed to predict the durability of SRS high-level waste glasses with higher sludge content than Purex 4. A melter run, designated Purex 4 Remediation, was performed using the 774 Research Melter to determine if the initial PCCS target composition determined for Purex 4 would produce acceptable glass whose durability could be accurately modeled by the DWPF glass durability algorithm. Reagent grade oxides and carbonates were added to Purex 4 melter feed stock to simulate a higher sludge loading. Each canister of glass produced was sampled and the glass durability was determined by the Product Consistency Test method. This document details the durability data and subsequent analysis.