Skip to main content
SpringerLink
Log in

Leaching of Whole, Defected Used Candu™ Fuel Elements in Saline Solutions Under Argon Pressure

  • Published:
MRS Online Proceedings Library Aims and scope

Abstract

In the context of the Canadian Nuclear Fuel Waste Management Program, experiments were performed in which whole, intentionally defected used CANDU™ fuel elements were exposed to deoxygenated saline solutions at 100°C for 484 days. Results suggest that both90Sr and99Tc are preferentially released from grain boundaries and that85Kr release is a good measure of the extent of grain-boundary dissolution. Severe grain-boundary attack in particular areas of the fuel is also evident from scanning electron microscope observations. It is hypothesized that such localized attack is related to fuel porosity. Because of its poor corrosion performance in saline solutions, the Zircaloy sheath cannot be considered as a radionuclide release barrier.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

References

  1. S.Stroes-Gascoyne, L.H.Johnson, P.A.Beeley and D.M.Sellinger in Scientific Basis for Nuclear Waste Management IX, edited by L.O.Werme, (Proc. MRS, Pittsburgh, PA 1986) p.317

    Google Scholar 

  2. S.Stroes-Gascoyne, L.H.Johnson and D.M.Sellinger, Nucl.Tech. 77, 320 (1987)

    Article  CAS  Google Scholar 

  3. L.H.Johnson and D.W.Shoesmith in Radioactive Waste Forms of the Future, edited by W.Lutze and R.Ewing, (New Holland) in press.

  4. L.H.Johnson, D.W.Shoesmith and S.Stroes-Gascoyne in Scientific Basis for Nuclear Waste Management XI, edited by M.Apted and R.E.Westerman, (Proc. MRS , Pittsburgh, PA 1988) p.99

    Google Scholar 

  5. L.H.Johnson, S.Stroes-Gascoyne, J.D.Chen, M.E.Attas, D.M.Sellinger and H.G.Delaney in Proc. Topical Meeting on Fission Product Behaviour and Source Term Research, Snowbird, Utah, 1984.

  6. D.R.M.Abry, R.G.F Abry, K.V.Ticknor and T.T.Vandergraaf, Atomic Energy of Canada Limited Technical Record TR-189 (1982)

  7. S. Stroes-Gascoyne and D.M. Sellinger in Proc. International Conference on CANDU Fuel, Chalk River, Ont. 1986, edited by I.J. Hastings, p. 383.

  8. M.J.F Notley, Nucl. Technol. 44, 445 (1979).

    Article  CAS  Google Scholar 

  9. D.M.Himmelblau, J.Chem. and Eng. Data 5, 10 (1960)

    Article  CAS  Google Scholar 

  10. L.O.Werme and R.S.Forsythe in Scientific Basis for Nuclear Waste Management XI, edited by M.Apted and R.E.Westerman, (Proc. MRS, Pittsburgh, PA 1988) p.443

    Google Scholar 

  11. B.Allard and B.Torstenfelt in KBS Technical Reports TR-83-60 (1983) SKF, Stockholm

  12. I.J.Hastings in Atomic Energy of Canada Limited Report AECL-Misc-249 (1982).

Download references

Author information

Authors and Affiliations

  1. Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, ROE ILO, Pinawa, Manitoba, Canada

    S. Stroes-Gascoyne, L. H. Johnson, J. C. Tait & D. M. Sellinger

Authors
  1. S. Stroes-Gascoyne
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. L. H. Johnson
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. J. C. Tait
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. D. M. Sellinger
    View author publications

    You can also search for this author in PubMed Google Scholar

Rights and permissions

Reprints and permissions

About this article

Cite this article

Stroes-Gascoyne, S., Johnson, L.H., Tait, J.C. et al. Leaching of Whole, Defected Used Candu™ Fuel Elements in Saline Solutions Under Argon Pressure. MRS Online Proceedings Library 127, 301–307 (1988). https://doi.org/10.1557/PROC-127-301

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1557/PROC-127-301

Search

Navigation