Hostname: page-component-745bb68f8f-d8cs5 Total loading time: 0 Render date: 2025-02-09T00:20:17.857Z Has data issue: false hasContentIssue false
  • English
  • Français

Dissolution Kinetics of UO2. I. Flow-Through tests on UO2.00 Pellets and Polycrystalline Schoepite Samples in Oxygenated, Carbonate/Bicarbonate Buffer Solutions at 25°C

Published online by Cambridge University Press:  25 February 2011

Son N. Nguyen ,
Homer C. Weed ,
Herman R. Leider  and
Ray B. Stout
Son N. Nguyen
Affiliation:
Lawrence Livermore National Laboratory, P. O. BOX 808, Livermore, CA 94550
Homer C. Weed
Affiliation:
Lawrence Livermore National Laboratory, P. O. BOX 808, Livermore, CA 94550
Herman R. Leider
Affiliation:
Lawrence Livermore National Laboratory, P. O. BOX 808, Livermore, CA 94550
Ray B. Stout
Affiliation:
Lawrence Livermore National Laboratory, P. O. BOX 808, Livermore, CA 94550
Get access

Abstract

The modelling of radionuclide release from waste forms is an important part of the performance assessment of a potential, high-level radioactive waste repository. Since spent fuel consists of UO2 containing actinide elements and other fission products, it is necessary to determine the principal parameters affecting UO2 dissolution and quantify their effects on the dissolution rate before any prediction of long term release rates of radionuclides from the spent fuel can be made.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 257: Symposium – Scientific Basis for Nuclear Waste Management XV , 1991 , 339
Copyright
Copyright © Materials Research Society 1992

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] Grambow, B. Spent Fuel Dissolution and Oxidation. An Evaluation of Literature Data, (SKB Technical Report 89-13 1989).Google Scholar
[2] Knauss, K.G. and Wolery, T.J., Geochim. Cosmochim. Acta 53, 1493 (1989).CrossRefGoogle Scholar
[3] Knauss, K.G., Bourcier, W.L., McKeegan, K.D., Merzbacher, C.I., Nguyen, S.N., Ryerson, F.J., Smith, D.K., Weed, H.C., and Newton, L., Dissolution Kinetics of a Simple Analogue Nuclear Waste Glass as a Function of pH. Time. and Temperature, (MRS Symposium Proceedings 176, 1990) p. 371.Google Scholar
[4] Wilson, C.N. and Gray, W.J., presented at the 1st Annual International High-Level Radioactive Waste Management Conference, Las Vegas, April 1990.Google Scholar
[5] Aagaard, P. and Helgeson, H.C., Amer. J. Sci. 282, 237 (1982).CrossRefGoogle Scholar
[6] Helgeson, H.C., Murphy, W.M., and Aagaard, P., Geochim. Cosmochim. Acta 48, 2405 (1984).CrossRefGoogle Scholar
[7] Lasaga, A.D., in Kinetics of Geochemical Processes. eds., Lasaga, A.C. and Kirkpatrick, R.J., (Mineral Soc. Amer., Reviews in Mineralogy 8, 1 1981).Google Scholar
[8] Aronson, S., in Uranium Dioxide: Properties and Nuclear Applications Bell, J., ed., United States Atomic Energy Commission, 1961, p. 377.Google Scholar
[9] Einziger, R.E., Test Plan for Long Term. Low Temperature Oxidation of BWR Spent Felu, PNL-6427, Pacific Northwest Laboratory (1988).CrossRefGoogle Scholar
[10] Wadsten, T., J. Nucl. Mat. 64, 315 (1977).CrossRefGoogle Scholar
[11] Gayer, K.H. and Leider, H., J. Am. Chem. Soc., 77, 1448 (1955).CrossRefGoogle Scholar
[12] Bolt, Beranek and Newman Software, version 2 (1989).Google Scholar
[13] Gray, W.J. and Wilson, C.N., personal communication.Google Scholar