Chemical corrosion of highly radioactive borosilicate nuclear waste glass under simulated repository conditions

Abstract

This review summarizes the results of the joint Japanese (Central Research Institute of Electric Power Industry, CRIEPI, Tokyo), Swiss (National Cooperative for the Storage of Radioactive Waste, NAGRA, Baden), Swedish (Swedish Nuclear Fuel and Waste Management Company, SKB, Stockholm) international ‘JSS’ project on the determination of the chemical durability of the French nuclear waste borosilicate glass, which was completed in 1988. Radioactive and nonradioactive glass specimens were investigated. A data base was created with results from glass corrosion tests performed with different water compositions, pH values, temperatures, sample surface areas (S), solution volumes (V), and flow rates. Glass corrosion tests were performed with and without bentonite and/or steel corrosion products present. Variation of the glass composition was taken into account by including the borosilicate glass ‘MW’ in the investigations, formulated by British Nuclear Fuels, plc. An understanding was achieved of the glass corrosion process in general, and of the performance of the French glass under various potential disposal conditions in particular. A special effort was made to establish a corrosion data base, using high S/V ratios in the experiments in order to understand the glass durability in the long term.

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References

  1. 1

    JSS-Projekt Phase I, SKB, Stockholm, Sweden, Technical Report 84–03 (1984).

  2. 2

    JSS-Projekt Phase II, SKB, Stockholm, Sweden, Technical Report 85–01 (1985).

  3. 3

    JSS-Projekt Phase III, SKB, Stockholm, Sweden, Technical Report 86–01 (1986).

  4. 4

    JSS-Projekt Phase IV, SKB, Stockholm, Sweden, Technical Report 87–01 (1987).

  5. 5

    B. Grambow, SKB, Stockholm, Sweden, Technical Report 87–02 (1987).

  6. 6

    JSS-Projekt Phase V, SKB, Stockholm, Sweden, Technical Report 88–02 (1988).

  7. 7

    M.J. Jercinovic and R. C. Ewing, SKB, Stockholm, Sweden, Technical Report 88–01 (1987).

  8. 8

    M. Miiller-Vonmoos and G. Kahr, Technischer Bericht 83–12, Nagra, Baden, Switzerland (1983).

  9. 9

    Anon., MCC-1P Static Leach Test Method, Nuclear Waste Materials Handbook, DOE/TIC-11400 (1981).

  10. 10

    Anon., MCC-4S Low-Flow-Rate Leach Test Method, Nuclear Waste Materials Handbook, PNL-3990 (1981).

  11. 11

    G. Bart, E. T. Aerne, and H. U. Zwicky, Nucl. Instr. Methods B17, 127 (1986).

    Article  Google Scholar 

  12. 12

    B. Grambow, Ph. D. Thesis, Freie Universität Berlin (1984), English transl. by E.I. du Pont de Nemours & Co., Aiken, SC, DP-tr-78 (1985).

  13. 13

    W. L. Kuhn and R. D. Peters (Proc. Mater. Res. Soc. Symp.), edited by D. G. Brookins (North-Holland, New York, 1983), Vol. 15, p. 167.

  14. 14

    R. M. Wallace and G. G. Wicks (Proc. Mater. Res. Soc. Symp.), edited by D. G. Brookins (North-Holland, New York, 1983), Vol. 15, p. 23.

  15. 15

    A. Barkatt, J. H. Simmons, and P. B. Macedo, Nucl. and Chem. Waste Management 2, 3 (1981).

  16. 16

    P. Aagaard and H. C. Helgeson, Amer. J. Science 281, 237 (1982).

    Article  Google Scholar 

  17. 17

    G. G. Wicks, J. A. Stone, G. T. Chandler, and S. Williams, Report DP-1728 (1986).

  18. 18

    W. Lutze, R. Müller, and W. Montserrat (Proc. Mater. Res. Soc. Symp.) (Materials Research Society, Pittsburgh, PA, 1988), Vol. 112, p. 575.

  19. 19

    D. L. Parkhurst, D. C. Thorstensen, and L. N. Plummer, PHREEQE, Water-Resources Investigations 80–96 (U.S. Geological Survey, Reston, VA), 1980. Extension to run precipitation controlled reactions by P. Offermann, HMI, Berlin, FRG (1983), updated with the MINTEQ data base by W. Howden and K. Kruppka, PNL, Richland, WA (1984).

  20. 20

    B. Fritz and M. Kam, SKB Stockholm, Sweden Technical Report 85–10 (1985).

  21. 21

    H. Wanner (Proc. Mater. Res. Soc. Symp.), edited by L.O. Werme (Materials Research Society, Pittsburgh, PA, 1986), Vol. 50, p. 509.

  22. 22

    F. Lanza and C. Ronsecco (Proc. Mater. Res. Soc. Symp.), edited by W. Lutze (Materials Research Society, Pittsburgh, PA, 1982), Vol. 11, p. 173.

  23. 23

    G. L. McVay and C. Q. Buckwalter, J. Am. Ceram. Soc. 66, 170 (1983).

    CAS  Article  Google Scholar 

  24. 24

    J. W. Shade, L. R. Pederson, and G. L. McVay, Advances in Ceramics VIII, edited by G. G. Wicks and W. A. Ross (The Am. Ceram. Soc, Columbus, OH, 1983), p. 358.

  25. 25

    G. Malow, W. Lutze, and R. C. Ewing, J. Non-Cryst. Solids 67, 305 (1984).

    CAS  Article  Google Scholar 

  26. 26

    W. Lutze, G. Malow, R. C. Ewing, M. Jercinovic, and K. Keil, Nature 314, 252(1985).

    CAS  Article  Google Scholar 

  27. 27

    R. C. Ewing and M. J. Jercinovic (Proc. Mater. Res. Soc. Symp.), edited by J. K. Bates and W. B. Seefeldt (Materials Research Society, Pittsburgh, PA, 1987), Vol. 84, p. 67.

  28. 28

    S. P. Jakobsson and J. G. Moore, Geological Society of America Bulletin 97, 648 (1986).

    CAS  Article  Google Scholar 

  29. 29

    B. Grambow, M. J. Jercinovic, R. C. Ewing, and C.D. Byers (Proc. Mater. Res. Soc. Symp., 1986), edited by L. O. Werme, Vol. 50, p. 263.

  30. 30

    B. Grambow, W. Lutze, R. C. Ewing, and L. O. Werme (Proc. Mater. Res. Soc. Symp., 1986), edited by M. J. Apted and R. E. Westerman, Vol. 112, p. 531.

  31. 31

    S. J. Zavoshy, P. L. Chambré, and T. H. Pigford (Proc. Mater. Res. Soc. Symp., 1985), edited by C. M. Jantzen, J. A. Stone, and R. C. Ewing, Vol. 44, p. 311.

  32. 32

    L. L. Hench, L. O. Werme, and A. Lodding (Proc. Mater. Res. Soc. Symp., 1982), edited by W. Lutze, Vol. 11, p. 153.

  33. 33

    A. Barkatt, P. B. Macedo, B. C. Gibson, and C.J. Montrose (Proc. Mater. Res. Soc. Symp., 1985), edited by C. M. Jantzen, J. A. Stone, and R. C. Ewing, Vol. 44, p. 3.

  34. 34

    B. Grambow (Proc. Mater. Res. Soc. Symp., 1985), edited by C.M. Jantzen, J. A. Stone, and R. C. Ewing, Vol. 44, p. 15.

  35. 35

    W. Lutze, in Radioactive Waste Forms for the Future, edited by W. Lutze and R. C. Ewing (North-Holland, Amsterdam, 1988), pp. 123–130.

  36. 36

    W. Lutze and R. C. Ewing, in Radioactive Waste Forms for the Future, edited by W. Lutze and R. C. Ewing (North-Holland, Amsterdam, 1988), pp. 699–740.

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Werme, L., Björner, I.K., Bart, G. et al. Chemical corrosion of highly radioactive borosilicate nuclear waste glass under simulated repository conditions. Journal of Materials Research 5, 113 (1990). https://doi.org/10.1557/JMR.1990.1130

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