Hostname: page-component-8448b6f56d-tj2md Total loading time: 0 Render date: 2024-04-25T03:54:37.896Z Has data issue: false hasContentIssue false
  • English
  • Français

Accounting for EBR-II Metallic Waste Form Degradation in TSPA

Published online by Cambridge University Press:  11 February 2011

W. L. Ebert ,
M. A. Lewis ,
T. L. Barber  and
S. G. Johnson
W. L. Ebert
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439
M. A. Lewis
Affiliation:
Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439
T. L. Barber
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403
S. G. Johnson
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403
Get access

Abstract

A metallic waste form (MWF) will be used to immobilize cladding hulls from spent sodium-bonded nuclear fuel rods. Laboratory tests were conducted to determine if the HLW glass degradation rate model used in Total System Performance Assessment (TSPA) calculations can be used as an upper bound for the degradation rate of the MWF. Static tests were conducted with monolithic MWF samples in pH buffer solutions to measure the degradation rates at 50, 70, and 90°C. The measured degradation rates of the MWF were compared to the rates calculated with the HLW glass degradation model. The degradation rates were calculated as the product of the specific dissolution rates and the anticipated exposed surface areas of glass and MWF in a breeched canister. This comparison showed that the rate calculated using the HLW glass degradation model bounds the rates measured for the MWF at all pH values and temperatures. These results support the potential use of HLW glass as a surrogate for MWF degradation for the purpose of performance assessment.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 757: Symposium II – Scientific Basis for Nuclear Waste Management XXVI , 2002 , II4.7
Copyright
Copyright © Materials Research Society 2003

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

REFERENCES

1. McDeavitt, S. M., Abraham, D. P., and Park, J. Y., J. Nucl. Mater. 257, 21 (1998).Google Scholar
2. Ebert, W. L., Cunnane, J. C., and Thornton, T. A., Proceedings of the 9th International High-Level Radioactive Waste Management Conference, April 29 – May 3, 2001, Las Vegas, NV, CD-ROM Section I-10 (2001).Google Scholar
3. Standard Test Methods for Determining Chemical Durability of Nuclear Waste Glasses: The Product Consistency Test (PCT), Standard C1285–99, Annual Book of ASTM Standards Vol. 12.01, American Society for Testing and Materials, West Conshohocken, PA.Google Scholar
4. Johnson, S. G., Keiser, D. D., Frank, S. M., DiSanto, T., Warren, A.R., and Noy, M., Mat. Res. Soc. Symp. Proc. 608, 589 (2000).Google Scholar
5. Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste, American Society for Testing and Materials Standard C1220, Annual Book of ASTM Standards, Vol 12.01, American Society for Testing and Materials, West Conshohocken, PA (1999).Google Scholar