Element Profiling by Secondary Ion Mass Spectrometry of Surface Layers in Glasses

  • A. Lodding
  • H. Odelius
  • D. E. Clark
  • L. O. Werme
Conference paper
Part of the Mikrochimica Acta Supplementum book series (MIKROCHIMICA, volume 11)


In the nuclear energy program of several countries, re-processed reactor waste is to be dissolved in glass for subsequent storage in geological burial sites (see e.g. 1). Waste form glasses must meet the demands of low viscosity liquid processing at relatively low temperatures; consideration has therefore mainly been given to alkali borosilicate (ABS) glasses. The waste containing processed glass is to satisfy the requirement of high corrosion resistance (low leachability) in interaction with water and with various components of the storage system.


Relative Sensitivity Factor Nuclear Waste Management Sample Voltage Reactor Waste Nuclear Energy Program 
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  1. 1.
    Scientific Basis for Nuclear Waste Management (V. W. Lutze, ed.). New York: North-Holland 1982.Google Scholar
  2. 2.
    Materials Characterization Center, DOE/TIC-11400, Pacific Northwest Laboratory, Richland, Washington 1982.Google Scholar
  3. 3.
    L. Werme, L. L. Hench, and A. Lodding, in Ref.1, p. 135.Google Scholar
  4. 4.
    L. L. Hench, A. Lodding, and L. Werme, J. Nucl. Materials 125, 273 (1984).CrossRefGoogle Scholar
  5. 5.
    A. Lodding, L. L. Hench, and L. Werme, J. Nucl. Materials 125, 280 (1984).CrossRefGoogle Scholar
  6. 6.
    L. L. Hench, L. Werme, and A. Lodding, J. Nucl. Materials 126, 226 (1984).CrossRefGoogle Scholar
  7. 7.
    A. Lodding, in: Rev. on Anal. Chemistry ( L. Niinistö, ed.). Budapest: Akademiai Kiadö 1982.Google Scholar
  8. 8.
    P. J. Hayward, W. H. Hocking, F. E. Doern, and E. V. Cecchetto, in Ref. 1, p. 319.Google Scholar
  9. 9.
    A, Lodding and H. Odelius, Mikrochim. Acta [Wien], Suppl. 10, 21 (1983).Google Scholar
  10. 10.
    H. Odelius, A. Lodding, L. Werme, and D. Clark, Scanning Electr. Microsc. 85 - 111. 927 (1985).Google Scholar
  11. 11.
    D. E. Clark, A. Lodding, H. Odelius, and L. O. Werme, submitted to J. Nucl. Materials.Google Scholar
  12. 12.
    R. H. Doremus, Nucl. & Chem. Waste Manag. 2, 119 (1981).Google Scholar
  13. 13.
    C. A. Andersen and J. R. Hinthorne, Anal. Chem. 45, 1421 (1973).CrossRefGoogle Scholar
  14. 14.
    U. Södervall, H. Odelius, and A. Lodding, to be published. The measurements have yielded nLi = 0.36 ±0.12 and nSi = 1.1 ±0.4.Google Scholar
  15. 15.
    J. C. Lorin, A. Havette, and G. Slodzian, in: SIMS III (A. Benninghoven, J. Giber, J. Läszlo, M. Riedel, and H. W. Werner, eds.). Springer Ser. Chem. Phys. 19, Berlin- Heidelberg-New York: Springer 1982, p. 140.Google Scholar
  16. 16.
    D. E. Newbury, in: SIMS II (A. Benninghoven, C. E. Evans, R. A. Powell, R. Shimizu, and H. A. Storms, eds.). Springer Ser. Chem. Phys. 9, Berlin-Heidelberg- New York: Springer 1979, p. 53.Google Scholar
  17. 17.
    M. Schreiner, G. Stingeder, and M. Grasserbauer, Fresenius’ Z. Anal. Chem. 319, 600 (1984).Google Scholar
  18. 18.
    L. L. Hench, A. Lodding, and L. L. Werme, to be published in J. Nucl. Materials.Google Scholar

Copyright information

© Springer-Verlag 1985

Authors and Affiliations

  • A. Lodding
    • 1
  • H. Odelius
    • 1
  • D. E. Clark
    • 2
  • L. O. Werme
    • 3
  1. 1.Physics DepartmentChalmers University of TechnologyGothenburgSweden
  2. 2.Department of Materials Science and EngineeringUniversity of FloridaGainesvilleUSA
  3. 3.Swedish Nuclear Fuel and Waste Management Co.StockholmSweden

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