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Microstructure and Leaching Characteristics of a Technetium Containing Metal Waste Form

Published online by Cambridge University Press:  10 February 2011

S. G. Johnson ,
D. D. Keiser ,
M. Noy ,
T. O'Holleran  and
S. M. Frank
S. G. Johnson
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
D. D. Keiser
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
M. Noy
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
T. O'Holleran
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
S. M. Frank
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
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Abstract

Argonne National Laboratory is developing an electrometallurgical treatment for spent fuel from the experimental breeder reactor II. A product of this treatment process is a metal waste form that incorporates the stainless steel cladding hulls, zirconium from the fuel and the fission products that are noble to the process, i.e., Tc, Ru, Pd, Rh, Ag. The nominal composition of this waste form is stainless steel/15 wt% zirconium/ 1–4 wt% noble metal fission products. The behavior of technetium is of particular importance from a disposal point of view for this waste form due to its long half life, 2.14E5 years, and its mobility in groundwater. To address these concerns a limited number of spiked metal waste forms were produced containing Tc. These surrogate waste forms were then studied using scanning electron microscopy (SEM) and selected leaching tests.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 556: Symposium QQ – Scientific Basis for Nuclear Waste Management XXII , 1999 , 953
Copyright
Copyright © Materials Research Society 1999

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References

REFERENCES

[1] Ackerman, J. P., McDeavitt, S. M., Pereira, C., Simpson, L. J., ANS Proceedings “Third Topical Meeting DOE Spent Nuclear Fuel and Fissile Materials Management”, Charleston, SC, 699 (1998).Google Scholar
[2] Prog. Nucl. Energy, 31 (1997), the entire volume.Google Scholar
[3] Barkatt, Aa., Macedo, P. B., Gibson, B. C., Mowad, R., Sousanpour, W., Barkatt, Al., Boroomand, M. A., Adel-Hadadi, M. Rogers, V. L., Nucl. and Chem. Waste Management ‘85, Vol.1, 471 (1985).Google Scholar
[4] Barkatt, Aa., Macedo, P. B., Sousanpour, W., Barkatt, Al., Boroomand, M. A., Fisher, C. F., Shirron, J. J., Szoke, P., Rogers, V. L., Nucl. and Chem. Waste Management, 4, 153 (1983).Google Scholar
[5] Mendel, J., E., ed., Final Report of the Defense High-Level Waste Leaching Mechanisms Program, PNL-5157 (1984).Google Scholar
[6] C1220-92, “Static Leaching of Monolithic Waste For Disposal of Radioactive Waste”, ASTM, Philadelphia (1995).Google Scholar
[7] Bradley, D. J., Harvey, C. O., Turcotte, R. P., “Leaching of Actinides and Technetium from Simulated High-Level Waste Glass”, PNL-3152 (1979).Google Scholar
[8] Fortner, J. A., Bates, J. K., Mat. Res. Soc., 412, 205 (1997).Google Scholar
[9] Hart, K. P., Vance, E. R., Day, R. A., Begg, B. D., Angel, P. J., Jostens, A., Mat. Res. Soc., 412, 281 (1997).Google Scholar
[10] Ringwood, A. E., Kesson, S. E., Reeve, K. D. Levins, D. M., Ramm, E. J., in “Radioactive Waste Forms for the Future”, Lutze, W. and Ewing, R. C., eds., North-Holland, Amsterdam, 233 (1988).Google Scholar