Constraints by Experimental Data for Modeling of Radionuclide Release from Spent Fuel


Comparison of spent fuel corrosion data from nuclear waste management projects in Canada, Sweden and the USA strongly suggests that the release of 90Sr to the leachant can be used as a measure of the degradation (oxidation/dissolution) of the fuel matrix. A surprisingly quantitative similarity in the 90Sr release data for fuel of various types (BWR, PWR, Candu), linear power ratings and burnups leached under oxic conditions was observed in the comparison. After 1000 days of leachant contact, static or sequential, the fractional release rates for 90Sr (and for cesium nuclides) were of the order of 10-7/d.

The rate of spent fuel degradation (alteration) under oxic conditions can be considered to be controlled either by the growth rates of secondary alteration products, by oxygen diffusion through a product layer, by the rate of formation of radiolytic oxidants or by solubility-controlled dissolution of the matrix. These processes are discussed. Methods for determining upper limits for long-term 90Sr release, and hence fuel degradation, have been derived from the experimental data and consideration of radiolytic oxidant production.

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  1. [1]

    N.C. Garisto, E.R. Vance, S. Stroes-Gascoyne and L.H. Johnson, “Instant Release Fractions for the Assessment of Used Nuclear Fuel Disposal” AECL-9892, Atomic Energy of Canada (1989)

  2. [2]

    H. Kleykamp, J. Nucl. Mater., 131 (1985) p. 221

    CAS  Article  Google Scholar 

  3. [3]

    L.O. Werme and R.S. Forsyth, Mat. Res. Soc. Symp. Proc. 112, (Materials Research Society, Pittsburgh, PA 15237, 1988) pp. 443–452

  4. [4]

    R.S. Forsyth, L.O. Werme and J. Bruno, J. Nucl. Mater. 138 (1986) pp. 1–15

  5. [5]

    S. Stroes-Gascoyne, L.H. Johnson, P.A. Beeley, and D.M. Sellinger, Mat. Res. Soc. Symp. Proc. 50, (Materials Research Society, Pittsburgh, PA 15237, 1985) pp. 317–326

  6. [6]

    B.M. Jeffery, J. Nucl. Mater. 22 (1967) pp. 33–40

  7. [7]

    H. Kleykamp, J.O. Paschoal, R. Pejsa, and F. Thummler, J. Nucl. Mater. 130 (1985) pp 426–433

  8. [8]

    L. Thomas, pers. communication (1989)

  9. [9]

    R.S. Forsyth, K. Svanberg and L. Werme, Mat. Res. Soc. Symp. Proc. 26, (Materials Research Society, Pittsburgh, PA 15237, 1984) pp. 179–190

  10. [10]

    L. Johnson, K.I. Burns, H. Joling and C.J. Moore, “The Dissolution of Irradiated UO2 fuel unde Hydrothermal Oxidizing Conditions”, TR-128, Atomic Energy of Canada (1981)

  11. [11]

    L.H. Johnson, D.W. Shoesmith, G.E. Lunansky, M.B. Bailey, M.B. and P.R. Tremaine, Nucl. Technology 56, (1982) p. 238

  12. [12]

    L.H. Johnson, Proceedings of the 19th information meeting of the nuclear fuel waste management program, TR-350, Atomic Energy of Canada (1985) pp. 239–248

  13. [13]

    T.T. Vandergraaf, “Leaching of Irradiated U02 Fuel”, TR-100, Atomic Energy of Canada (1980)

  14. [14]

    Studsvik Fuel Laboratory, to be published.

  15. [15]

    B. Grambow, “Spent fuel: Dissolution and oxidation. An evaluation of literature data”, Technical Report 89-13, SKB, Stockholm, Sweden (1989)

  16. [16]

    C.N. Wilson, C.J. Bruton, “Studies on Spent Fuel Dissolution Behavior Under Yucca Mountain Repository Conditions”, UCRL-100223, Lawrence Livermore National Laboratory, Livermore, CA. 94559 (1989)

  17. [17]

    D.W. Shoesmith, S. Sunder, B.M. Ikeda, and F. King, Mat. Res. Soc. Symp. Proc. 127, (Materials Research Society, Pittsburgh, PA 15237, 1989) pp. 279–293

  18. [18]

    R. Wang, “Spent Fuel Special Studies Progress Report”, PNL-3566, Pacific Northwest Laboratory, Richland, WA. 99352 (1981)

  19. [19]

    J. Bruno and A. Sandino, Mat. Res. Soc. Symp. Proc. 127, (Materials Research Society, Pittsburgh, PA 15237, 1989) pp. 871–878

  20. [20]

    M.J. Apted, A.M. Liebetrau and D.W. Engel, “The Analytical Repository Source-Term (AREST) Model: Analysis of Spent Fuel as a Nuclear Waste Form”, Report PNL-6347, Battelle Pacific Northwest Laboratory, Richland, WA 99352, USA (1989).

  21. [21]

    K. Ollila, “Dissolution Mechanism of U02 at Various Parametric Conditions”, Report YJT-88-04, Technical Research Centre of Finland, Reactor Laboratory (1988)

  22. [22]

    P.A.G. O’Hare, B.M. Lewis and S.N. Nguyen, J. Chem. Thermodynamics, 20, (1988) pp. 1287–1296

  23. [23]

    J. Bruno and I. Puigdomenech, Mat. Res. Soc. Symp. Proc. 127, (Materials Research Society, Pittsburgh, PA 15237, 1989) pp. 887–896

  24. [24]

    H. Christensen and E. Bjergbakke, “Radiolysis of groundwater from spent fuel”, SKBF-KBS TR 82-18, SKB, Stockholm, Sweden (1982).

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Grambow, B., Werme, L.O., Forsyth, R.S. et al. Constraints by Experimental Data for Modeling of Radionuclide Release from Spent Fuel. MRS Online Proceedings Library 176, 465 (1989).

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