Hostname: page-component-cd9895bd7-jn8rn Total loading time: 0 Render date: 2024-12-27T01:46:18.886Z Has data issue: false hasContentIssue false

Characteristics of Preliminary Waste Forms for Icpp Low Activity Waste (Law) Fractions after Radionuclide Separations

Published online by Cambridge University Press:  15 February 2011

Krishna Vinjamuri*
Affiliation:
Idaho National Engineering Laboratory Lockheed Idaho Technologies Company, MS 5213, P. 0. Box 1625, Idaho Falls, Idaho 83415–5213
Get access

Abstract

Currently, at the Idaho Chemical Processing Plant (ICPP) there are about 6800 m3 of liquid sodium-bearing and liquid high-level wastes (HLW), and 3800 m3 of solid calcined HLW. One of the waste processing options under consideration includes separation of the HLW into high activity and low activity (LAW) wastes, followed by immobilization. Preliminary glasses were synthesized for the sodium-bearing, alumina-bearing, and the zirconia-bearing LAW fractions after radionuclide separations. The glasses were formed by crucible melting of a mixture of reagent chemicals representative of the LAW waste streams and frit additives at 1200 °C for 5 hours, followed by overnight annealing at 550 °C and furnace cooling of the melt. These glasses were characterized for density, elastic property, viscosity, chemical durability, structural parameters, and glass phase separation. The results are compared with that of the Hanford's standard glass ARM-i, Savannah River's benchmark glass EA, and the ICPP's grout waste form prepared using the simulated non-radioactive sodium-bearing waste fraction.

Type
Research Article
Copyright
Copyright © Materials Research Society 1996

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. Murphy, J. A., Pincock, L. F., and Christiansen, I. N., ICPP Radioactive Liquid And Calcine Waste Technologies Evaluation Final Report and Recommendations, INEL-94/0119, April 1995.Google Scholar
2. Vinjamuri, Krishna, Glass Waste Forms for the Na-bearing High Activity Waste Fractions, INEL-95/0214, June 1995.Google Scholar
3. Jantzen, C. M., “First Principle Process-Product Models For Vitrification of Nuclear Waste: Relationship of Glass Composition To Glass Viscosity, Resistivity, Liquid Temperature, and Durability, Ceramic Transactions, Volume 23, Nuclear Waste Management IV, American Ceramic Society, Inc., 1991, pp. 3751.Google Scholar
4. Goldston, W. T. and Plodinec, M. J., “The DWPF Strategy for Producing an Acceptable Product,” Ceramic Transactions, Volume 23, Nuclear Waste Management IV, American Ceramic Society, Inc., 1991, pp. 443452.Google Scholar
5. Vinjamuri, K., GlassForm: A Computer Program to Predict Glass Melt Viscosity. Melt Resistivity. Density, Chemical Durability and Glass Quality Indicators of Glass Waste Forms, to be published.Google Scholar
6. Berreth, J. R., Westinghouse Idaho Nuclear Company, to D. A. Knecht, Westinghouse Idaho Nuclear Company, Subject: Basic CERCOMP Instructions for Use, Personal Communication, February 1990.Google Scholar
7. Varshneya, A. K., Fundamentals of Inorganic Glasses, Academic Press, 1993.Google Scholar