Hostname: page-component-586b7cd67f-rcrh6 Total loading time: 0 Render date: 2024-12-01T10:43:16.569Z Has data issue: false hasContentIssue false

Liquidus Temperature and Crystallization Behavior of US Waste Glasses Investigated at KRI

Published online by Cambridge University Press:  15 February 2011

Albert S. Aloy
Affiliation:
FSUE RPA «V.G. Khlopin Radium Institute» (KRI) 2–nd Murinsky Ave., 28, St. Petersburg, 194021, Russian Federation
Alexander V. Trofimenko
Affiliation:
FSUE RPA «V.G. Khlopin Radium Institute» (KRI) 2–nd Murinsky Ave., 28, St. Petersburg, 194021, Russian Federation
Valery Z. Belov
Affiliation:
FSUE RPA «V.G. Khlopin Radium Institute» (KRI) 2–nd Murinsky Ave., 28, St. Petersburg, 194021, Russian Federation
James C. Marra
Affiliation:
Savannah River National Laboratory (SRNL) Savannah River Site, 999-W, Aiken, SC 29808, USA
Kevin M. Fox
Affiliation:
Savannah River National Laboratory (SRNL) Savannah River Site, 999-W, Aiken, SC 29808, USA
David Peeler
Affiliation:
Savannah River National Laboratory (SRNL) Savannah River Site, 999-W, Aiken, SC 29808, USA
John D. Vienna
Affiliation:
Pacific Northwest National Laboratory (PNNL) P. O. Box 999, Richland, WA, 99352, USA
Dong-Sang Kim
Affiliation:
Pacific Northwest National Laboratory (PNNL) P. O. Box 999, Richland, WA, 99352, USA
Get access

Abstract

As a part of the optimization study for achieving the highest possible Hanford and Savannah River Site waste loading into acceptable borosilicate glasses, thirty glass compositions were selected for testing at KRI. These thirty test matrix glasses were designed to augment existing data within the compositional regions of interest with relatively high concentration of Al2O3 between 10 and 20 wt%.

This paper reports experimental data on liquidus temperature (TL) and crystallization behavior of all synthesized glasses as well as durability of quenched and heat-treated glasses. The results of this study will be used to develop glass formulations for specific DOE waste streams to maintain or meet waste loading and/or waste throughput expectations while satisfying critical process and product performance related constraints.

Type
Research Article
Copyright
Copyright © Materials Research Society 2009

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1 Gerdes, K.D., Harbour, J.R., Marra, J.C., Peeler, D.K. and etc. in Waste Management'07 Conf, February 25-March 1, 2007, Tuson, AZ. 2007. CD-ROM.Google Scholar
2 Li, H., Vienna, J.D., Hrma, P., Smith, D.E., Schweiger, M.J. in Sci. Basis for Nuclear Waste Management XX, edited by Gray, W.J. and Triay, I.R., (Mat. Res. Soc. Proc. 465, 1997), pp. 261268.Google Scholar
3 Aloy, A.S., Vienna, J.D., Soshnikov, R.A., Elliott, M., Holtzchieter, E.W. in Waste Management'06 Conf, February 26-March 2, 2006, Tuson, AZ. 2006. CD-ROM.Google Scholar
4 Hrma, P., Vienna, J.D., Crum, J., Piepel, G., Mika, M. in Sci. Basis for Nuclear Waste Management XXIII, edited by Smith, R.W. and Shoesmith, D.W., (Mat. Res. Soc. Proc. 608, 2000), pp. 671-676.Google Scholar
5 ASTM, 2002. Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses: The Product Consistency Test (PCT), ASTM C 1285-02, Annual Book of ASTM Standards, Philadelphia, Pennsylvania.Google Scholar