Hostname: page-component-848d4c4894-p2v8j Total loading time: 0 Render date: 2024-05-06T23:05:01.957Z Has data issue: false hasContentIssue false

The Effect of Increased Waste Loading on the Durability of High Level Waste Glass

Published online by Cambridge University Press:  01 February 2011

Chris Brookes
Affiliation:
christopher.m.brookes@sellafieldsites.com, Sellafield Ltd., High Level Waste Plants, Seascale, United Kingdom
Mike Harrison
Affiliation:
mike.t.harrison@nnl.co.uk, National Nuclear Laboratory, Seascale, United Kingdom
Andrew Riley
Affiliation:
andrew.d.riley@sellafieldsites.com, Sellafield Ltd., High Level Waste Plants, Seascale, United Kingdom
Carl James Steele
Affiliation:
carl.j.steele@sellafieldsites.com, Sellafield Ltd., High Level Waste Plants, Seascale, United Kingdom
Get access

Abstract

This paper describes the results from static leach tests using the ASTM International standard Materials Characterisation Centre (MCC-1) and Product Consistency Test (PCT) protocols for inactive High Level Waste (HLW) glasses fabricated at full scale on the Sellafield Vitrification Test Rig. The samples comprised monoliths and powders of a 75:25 Oxide:Magnox Blend glass with 31 wt% waste incorporation and a Magnox-only glass with 35 wt% waste incorporation. The tests were carried out in de-ionized water at 90 °C for durations up to 42 days and normalized mass losses calculated.

The results of MCC-1 and PCT tests on both 31 wt% Blend and 35 wt% Magnox glasses, showing measurable differences to the corresponding standard 25 wt% waste incorporation glasses, are presented. A series of Scanning Electron Microscopy (SEM) investigations were also undertaken. The variation in composition and thickness of the alteration layer with sample type and duration is reported.

Type
Research Article
Copyright
Copyright © Materials Research Society 2010

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

1ASTM C1220-98: Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste.Google Scholar
2ASTM C1285-02: Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test (PCT).Google Scholar
3 Gin, S., Godon, N., Ribet, I., Jollivet, P., Minet, Y., Frugier, P., Vernaz, E., Cavedon, J. M., Bonin, B., and Quang, R. Do, Mat. Res. Soc. Symp. Proc. 824, 327332 (2004).Google Scholar
4 Iseghem, P. Van, Lemmens, K. Aertsens, M. Gin, S. Ribet, I. Grambow, B. Crovisier, J.L., Nero, M. Del, Curti, E. Schwyn, B. Luckscheiter, B. and McMenamin, T. Mat. Res. Soc. Symp. Proc. 932, 293304 (2006).Google Scholar
5NF-Pro Final Synthesis Report RTD Component 1: Dissolution and release from the waste matrix.Google Scholar
6 Curti, E. Crovisier, J. L. Morvan, G. and Karpoff, A. M. Applied Geochemistry 21, 11521168 (2006).Google Scholar
7 Zwicky, H. U. Grambow, B. Magrabi, C. Erne, E. T. Bradley, R. Barnes, B. Graber, Th. Mohos, M. and Werme, L. O. Mat. Res. Soc. Symp. Proc. 127, 129136 (1989).Google Scholar
8 Banba, T. Hagiya, H. Tamura, Y. Senoo, M. Yonezawa, C. and Carter, P, Analytical Sciences 14, 389394 (1998).Google Scholar
9 Frugier, P. Martin, C. Ribet, I. Advocat, T. and Gin, S. Journal of Nuclear Materials 346, 194207 (2005).Google Scholar