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Characterization of Composite Ceramic High Level Waste Forms

Published online by Cambridge University Press:  10 February 2011

S. M. Frank,
K. J. Bateman,
T. DiSanto,
S. G. Johnson,
T. L. Moschetti,
M. H. Noy and
T. P. O'Holleran
S. M. Frank
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403-2528
K. J. Bateman
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403-2528
T. DiSanto
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403-2528
S. G. Johnson
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403-2528
T. L. Moschetti
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403-2528
M. H. Noy
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403-2528
T. P. O'Holleran
Affiliation:
Argonne National Laboratory-West, P.O. Box 2528, Idaho Falls, ID 83403-2528
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Abstract

Argonne National Laboratory has developed a composite ceramic waste form for the disposition of high level radioactive waste produced during electrometallurgical conditioning of spent nuclear fuel. The electrorefiner LiCl/KCl eutectic salt, containing fission products and transuranics in the chloride form, is contacted with a zeolite material which removes the fission products from the salt. After salt contact, the zeolite is mixed with a glass binder. The zeolite/glass mixture is then hot isostatic pressed (HIPed) to produce the composite ceramic waste form. The ceramic waste form provides a durable medium that is well suited to incorporate fission products and transuranics in the chloride form. Presented are preliminary results of the process qualification and characterization studies, which include chemical and physical measurements and product durability testing, of the ceramic waste form.

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References

REFERENCES

1. Pereira, C., Lewis, M. A. and Ackerman, J. P., Spent Nuclear Fuel-Treatment Technologies Reno, NV, 1996.Google Scholar
2. Goff, K. M., Benedict, R. W., Bateman, K., Lewis, M. A., Pereira, C., Musick, C. A., International Topical Meeting on Nuclear and Hazardous Waste Management, Spectrum, Seattle, WA, 2436–2443 (1996).Google Scholar
3. Lewis, M. A., Fischer, D. F. and Smith, L. J., J. Am. Ceram. Soc., 76, (11), 2826–2832 (1993).Google Scholar
4. Pereira, C., Zyryanov, V. N., Lewis, M. A. and Ackerman, J. P., ANL Report ANL/CMT/CP-88168; DE96010799; CONF-9604124-3, pp. 1–12, (1996).Google Scholar
5. Lewis, M. A., Verna, S., Ackerman, J. P., Environmental Issues and Waste Management Technologies in Ceramic and Nuclear Industries, Eds., V., Jain and R., Palmer, Am. Ceram. Soc., Westerville, OH, 389–397 (1995).Google Scholar
6. Lewis, M. A., Fischer, D. F. and Murphy, C. D., Scientific Basis for Nuclear Waste Management, Beshatt, A. and Konyenburg, R.Van, Eds., Vol.333, pp. 277–284, Mat. Res. Soc., Pittsburg, OH (1994).Google Scholar
7. Lewis, M. A., Hash, M. C., Pereira, C. and Ackerman, J. P., ANL Report ANL/CMT/CP-88170; DE96010798; CONF-9604124-2, pp. 1–10, (1996).Google Scholar
8. Hash, M. C., Pereira, C., Lewis, M. A., Blaskovitz, R. J., Zyryanov, V. N. and Ackerman, J. P., ANL Report ANL/CMT/CP-88169; DE96010776; CONF-9604124-4, pp. 1–10, (1996).Google Scholar
9. U.S. Department of Energy, Office of Civilian Radioactive Waste Management, “Waste Acceptance System Requirements Document,” Report No. DOE/RW-035 1, Rev. 2, 1996.Google Scholar
10. ASTM C 1220-92, Standard Test Methods for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste. Annual Book of ASTM Standards, Philadelphia, PA, 1995.Google Scholar
11. ASTM C1285-94, Standard Test Methods for Determining Chemical Durability of Nuclear Waste Glasses: The Product Consistency Test (PCT). Annual Book of ASTM Standards, Philadelphia, PA, 1995.Google Scholar
12. Breck, D. W., Zeolite Molecular Sieves, (Wiley, New York. 1974), pp. 83–92, 202, 483–498.Google Scholar
13. Richardson, J. W. Jr., Mat. Res. Soc. Symp. Proc. Vol.465, 395 (1997).Google Scholar
14. Boersma, M. D., Am. Nuclear Soc., Vol.1, 131 (1984).Google Scholar