Hostname: page-component-586b7cd67f-2brh9 Total loading time: 0 Render date: 2024-11-25T15:48:01.075Z Has data issue: false hasContentIssue false
  • English
  • Français

Predictions of Radionuclide Migration Rates for a Subseabed Repository*

Published online by Cambridge University Press:  15 February 2011

L. H. Brush
L. H. Brush*
Affiliation:
Seabed Programs Division 4516, Sandia National Laboratories, Albuquerque, NM 87185
Get access

Abstract

Geochemical research carried out by the U.S. Subseabed Disposal Program is described. Data from studies of high temperature interactions between sediments and porewater (seawater), and of sorption and diffusion of radionuclides in oxidized, deep-sea sediments are used, along with results from heat transfer studies, to predict migration rates of radionuclides in a subseabed repository.

Preliminary results for most radionuclides in oxidized sediments are very encouraging: fission products with moderate values of KD (generally 10 to 10 ml/g), and actinides with high values of KD (generally 103 to 106 ml/g) would not migrate significant distances before decaying to innocous concentrations. 137Cs, 90Sr, and 239Pu are among this group. The results for anionic species are less encouraging, but preliminary work with reduced sediments indicates that Tc can be effectively isolated.

Planning for a field verification of these laboratory and modeling studies is also described.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 6: Symposium D – Scientific Basis for Nuclear Waste Management IV , 1981 , 287
Copyright
Copyright © Materials Research Society 1982

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.)

Footnotes

*

This work performed at Sandia National Laboratories supported by the U. S. Department of Energy under contract number DE–ACO4–76DP00789.

References

REFERENCES

1. Burger, L. L., Determining Criteria for the Disposal of Iodine – 129, PNL 3496, (Battelle Pacific Northwest Laboratories, Richland, WA. 1980).Google Scholar
2. Talbert, D. M., ed., Seabed Disposal Program Annual Report, January – December, 1975, SAND 76–0256 (Sandia National Laboratories, Albuquerque, NM 1976)Google Scholar
3. Talbert, D. M., ed., Subseabed Disposal Program Annual Report, January – December, 1976, Volume II: Principal Investigators' Reports, SAND 78–1359 (Sandia National Laboratories, Albuquerque, NM 1977).Google Scholar
4. Talbert, D. M., ed., Subseabed Disposal Program Annual Report, January – December, 1977, Volume II: Principal Investigators' Reports, SAND 77–1270 (Sandia National Laboratories, Albuquerque, NM 1979).Google Scholar
5. Talbert, D. M., ed., Subseabed Disposal Program Annual Report, January – December, 1978, Volume II: Principal Investigators' Reports, SAND 79–1618 (Sandia National Laboratories, Albuquerque, NM 1979).Google Scholar
6. Talbert, D. M., ed., Subseabed Disposal Program Annual Report, January – December, 1979, Volume II: (Parts 1 and 2) Principal Investigators' Reports, SAND 80–2577/II (Sandia National Laboratories, Albuquerque, NM 1981).Google Scholar
7. Hinga, K., ed., Subseabed Disposal Program Annual Report, January – December, 1980, Volume II: Principal Investigators' Reports, SAND 81–1095/II (Sandia National Laboratories, Albuquerque, NM 1981).Google Scholar
8. Seyfried, W. E. and Janecky, D. R., in [5], op. cit., pp. 547–562.Google Scholar
9. Seyfried, W. E., Thornton, E. C. and Janecky, D. R., in [6], op. cit., Part 1, pp. 163–258.Google Scholar
10. Seyfried, W. E. and Thornton, E. C., in [7], op. cit., Part 1, pp. 73–242.Google Scholar
11. Wolery, T. J., Calculation of Chemical Equilibrium Between Aqueous Solutions and Minerals: The EQ3/EQ6 Software Package, UCRL 52658, Lawrence Livermore National Laboratory, Livermore, CA 1979).Google Scholar
12. Erickson, K. L., in [4] op. cit., pp. 487–500.Google Scholar
13. Erickson, K. L.,in [5], op. cit., pp. 595–635.Google Scholar
14. Erickson, K. L.,in [6], op. cit., Part 1, pp. 301–322.Google Scholar
15. Erickson, K. L., in [7], op. cit., Part 1, pp. 305–322.Google Scholar
16. Heath, G. R., Epstein, G. and Prince, R. A., in [3], cp. cit., pp. 53–144.Google Scholar
17. Heath, G. R., Epstein, G.B., Leinen, M. and Prince, R. A., in [4], op. cit., pp. 33–188.Google Scholar
18. Heath, G. R., Laine, E.P., Epstein, G. B., Heggie, D., Leinen, M. and Prince, R. A., in [5],op. cit., pp. 121–236.Google Scholar
19. Heath, G. R., Leinen, M. and Epstein, G. B. in [6], op. cit., Part 2, pp. 31–186.Google Scholar
20. Kenna, B. T., in [7], op. cit., Part 1, pp. 243–252.Google Scholar
21. Schreiner, F., Fried, S. and Friedman, A., in [7], op. cit., Part 1, pp. 267–304.Google Scholar
22. Russo, A. J., Prediction of the Migration of Several Radionuclides in Ocean Sediments with the Carputer Code IONMIG - A Preliminary Report SAND 79–1666, Sandia National Laboratories, Albuquerque, NM 1980).Google Scholar
23. Bell, M. J., ORIGEN - The ORNL Isotype Generation and Depletion Code, ORNL – 4628 (Oak Ridge National Laboratories, Oak Ridge, TN 1973).Google Scholar
24. Gartling, D. K. and Hickox, C. E. Jr., MARIAH - A Finite Element Computer Program for Inccmpressible Porous Flow Problems, Volume I: Theoretical Background, SAND79–1622; Volume II: User's Manual, SAND 79–1623, Sandia National Laboratories, Albuquerque, NM in press).Google Scholar
25. Strickert, R., Friedman, A. M. and Fried, S., Nucl. Tech. 49, 253 (1980).Google Scholar
26. Schreiner, F., Fried, S. and Friedman, A., this volume.Google Scholar
27. Percival, C. M., McVey, D. F., Olson, L. O. and Silva, A. J., The Subseabed Disposal Program In Situ Heat Transfer Experiment (ISHTE), SAND80–0202 (Sandia National Laboratories, Albuquerque, NM in press).Google Scholar