Skip to main content Accessibility help

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

  • Bernd Grambow (a1), L.O. Werme (a2), R.S. Forsyth (a3) and J. Bruno (a4)


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 90 Sr 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.



Hide All
[1] Garisto, N.C., Vance, E.R., Stroes-Gascoyne, S. and Johnson, L.H., “Instant Release Fractions for the Assessment of Used Nuclear Fuel Disposal” AECL-9892, Atomic Energy of Canada (1989)
[2] Kleykamp, H., J. Nucl. Mater., 131 (1985) p. 221
[3] Werme, L.O. and Forsyth, R.S., Mat. Res. Soc. Symp. Proc. 112, (Materials Research Society, Pittsburgh, PA 15237, 1988) pp. 443452
[4] Forsyth, R.S., Werme, L.O. and Bruno, J., J. Nucl. Mater. 138 (1986) pp. 115
[5] Stroes-Gascoyne, S., Johnson, L.H., Beeley, P.A., and Sellinger, D.M., Mat. Res. Soc. Symp. Proc. 50, (Materials Research Society, Pittsburgh, PA 15237, 1985) pp. 317326
[6] Jeffery, B.M., J. Nucl. Mater. 22 (1967) pp. 3340
[7] Kleykamp, H., Paschoal, J.O., Pejsa, R., and ThUmmler, F., J. Nucl. Mater. 130 (1985) pp 426433
[8] Thomas, L., pers. communication (1989)
[9] Forsyth, R.S., Svanberg, K. and Werme, L., Mat. Res. Soc. Symp. Proc. 26, (Materials Research Society, Pittsburgh, PA 15237, 1984) pp. 179190
[10] Johnson, L., Burns, K.I., Joling, H. and Moore, C.J., “The Dissolution of Irradiated U02 fuel unde Hydrothermal Oxidizing Conditions”, TR-128, Atomic Energy of Canada (1981)
[11] Johnson, L.H., Shoesmith, D.W., Lunansky, G.E., Bailey, M.B., and, M.B. Tremaine, P.R., Nucl. Technology 56, (1982) p. 238
[12] Johnson, L.H., Proceedings of the 19th information meeting of the nuclear fuel waste management program, TR-350, Atomic Energy of Canada (1985) pp. 239248
[13] Vandergraaf, T.T., “Leaching of Irradiated U02 Fuel”, TR-100, Atomic Energy of Canada (1980)
[14] Studsvik Fuel Laboratory, to be published.
[15] Grambow, B., “Spent fuel: Dissolution and oxidation. An evaluation of literature data”, Technical Report 89-13, SKB, Stockholm, Sweden (1989)
[16] Wilson, C.N., Bruton, C.J., “Studies on Spent Fuel Dissolution Behavior Under Yucca Mountain Repository Conditions”, UCRL-100223, Lawrence Livermore National Laboratory, Livermore, CA. 94559 (1989)
[17] Shoesmith, D.W., Sunder, S., Ikeda, B.M., and King, F., Mat. Res. Soc. Symp. Proc. 127, (Materials Research Society, Pittsburgh, PA 15237, 1989) pp. 279293
[18] Wang, R., “Spent Fuel Special Studies Progress Report”, PNL-3566, Pacific Northwest Laboratory, Richland, WA. 99352 (1981)
[19] Bruno, J. and Sandino, A., Mat. Res. Soc. Symp. Proc. 127, (Materials Research Society, Pittsburgh, PA 15237, 1989) pp. 871878
[20] Apted, M.J., Liebetrau, A.M. and Engel, D.W., “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] Ollila, K., “Dissolution Mechanism of U02 at Various Parametric Conditions”, Report YJT-88-04, Technical Research Centre of Finland, Reactor Laboratory (1988)
[22] P.O'Hare, A.G., Lewis, B.M. and Nguyen, S.N., Chem, J.. Thermodynamics, 20, (1988) pp. 12871296
[23] Bruno, J. and Puigdomenech, I., Mat. Res. Soc. Symp. Proc. 127, (Materials Research Society, Pittsburgh, PA 15237, 1989) pp. 887896
[24] Christensen, H. and Bjergbakke, E., “Radiolysis of groundwater from spent fuel”, SKBF-KBS TR 82-18, SKB, Stockholm, Sweden (1982).


Full text views

Total number of HTML views: 0
Total number of PDF views: 0 *
Loading metrics...

Abstract views

Total abstract views: 0 *
Loading metrics...

* Views captured on Cambridge Core between <date>. This data will be updated every 24 hours.

Usage data cannot currently be displayed