Hostname: page-component-76fb5796d-2lccl Total loading time: 0 Render date: 2024-04-26T18:55:11.577Z Has data issue: false hasContentIssue false
  • English
  • Français

Corrosion of inconel-690 electrodes in waste glass melts

Published online by Cambridge University Press:  10 February 2011

H. Gan ,
A. C. Buechele ,
C.-W. Kim ,
X. Huang ,
R. K. Mohr  and
I. L. Pegg
H. Gan
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington, DC 20064
A. C. Buechele
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington, DC 20064
C.-W. Kim
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington, DC 20064
X. Huang
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington, DC 20064
R. K. Mohr
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington, DC 20064
I. L. Pegg
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington, DC 20064
Get access

Abstract

Inconel-690, a Cr-Ni-Fe-based “superalloy,” has become the material of choice for electrodes in joule-heated waste glass melters and is currently employed in the high-level nuclear waste vitrification systems at West Valley and DWPF, as well as in GTS Duratek's privatized M-Area mixed waste vitrification facility at Savannah River. Future applications of joule-heated vitrification technologies will necessitate an assessment of the limits of performance of this material under more demanding conditions than have been studied previously. In this work, Inconel 690 electrodes were tested in several simulated sodium-rich aluminosilicate waste glasses in wide ranges of AC current density, electrical waveform, temperature, and glass composition.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 556: Symposium QQ – Scientific Basis for Nuclear Waste Management XXII , 1999 , 287
Copyright
Copyright © Materials Research Society 1999

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] Palmer, R. A., "Interactions Between Candidate Melter Electrode Materials and Defense Waste Glass Melts," report for Rockwell International, Rockwell Hanford Operations RHOSA-173, September 1980.Google Scholar
[2] Bickford, D. F., Ondrejcin, R. S., Salley, L., “High-Temperature Materials for Radioactive Waste Incineration and Vitrification”,Advances in Ceramics, Nuclear Waste Managemen II 20 p. 65 (1986).Google Scholar
[3] Wang, E., Mohr, R. K., Buechele, A. C., and Pegg, I. L., "Current Density Effects on the Corrosion of ceramic and Metallic Electrode Materials in Waste Glasses," Scientific Basis for Nuclear Waste ManagementXIX, Eds. Murphy, W. M. and Knecht, D. A., MRS, Pittsburgh, PA, 412 181 (1996).Google Scholar
[4] Gan, H., Fu, L., Perez-Cardenas, F., Buechele, A. C., Mohr, R. K., Pegg, I. L. and Macedo, P. B. in Corrosion of Materials by Molten Glass, edited by Pecoraro, G. A., Marra, J. C. and Wenzel, J. T. (Ceramic Transactions, Volume 78, Indianapolis, Indiana, 1996) pp. 327–336 Google Scholar