Skip to main content
SpringerLink
Log in

Swelling behavior of U-Pu-Zr fuel

  • Published:
Metallurgical Transactions A Aims and scope Submit manuscript

Abstract

Recent fast reactor driver fuel tests in the Experimental Breeder Reactor II (EBR-II) have demonstrated good performance of U-Pu-Zr fuel alloys to burnups >15 at. pct. Postirradiation examination of these tests has yielded a large amount of fuel-swelling data and metallographic information. These data show that prior to making contact with the cladding tube, metallic alloy fuel swells rapidly due to its high fission-enhanced creep rate and irradiation growth. Measurements of macroscopic fuel slug growth during the entire fuel pin lifetime can now be understood by properly taking into account the irradiation environment and microstructural changes for the various alloy compositions. It has been determined that fission rate, temperature, and plutonium concentrations influence the observed macroscopic swelling rate.

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. J.H. Kittel and S.H. Pain:Proc. 2nd Int. Conf. on the Peaceful Uses of Atomic Energy, Genéve, Switzerland, 1958, vol. 5, pp. 500–09.

    CAS  Google Scholar 

  2. S.N. Buckley:Properties of Reactor Materials and the Effects of Radiation Damage, DJ. Littler, ed., Butterworth’s, London, 1962, pp. 413–16.1

    Google Scholar 

  3. M. Colin:Nucl. Technol., 1983, vol. 63, pp. 442–60.

    CAS  Google Scholar 

  4. R.D. Legget, B. Martel, Bierlein:Irradiation Behavior of High Purity Uranium, Hanford Laboratory, Richland, WA, Report HW-79559 1963.

    Google Scholar 

  5. S.N. Buckley: AERE Report R-5262, 1966, pp. 51-54.

  6. J. Coffinberry:The Metal Plutonium, University of Chicago Press, Chicago, IL, 1961, pp. 120–21.

    Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Experimental Breeder Reactor (EBR-11|Division, Argonne National Laboratory, 60439, Argonne, IL

    Gerard L. Hofman (Senior Metallurgist), R. G. Pahl (Metallurgist Engineer), C. E. Lahm (Mechanical Engineer) & D. L. Porter (Metallurgist)

Authors
  1. Gerard L. Hofman
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. R. G. Pahl
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. C. E. Lahm
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. D. L. Porter
    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

Hofman, G.L., Pahl, R.G., Lahm, C.E. et al. Swelling behavior of U-Pu-Zr fuel. Metall Trans A 21, 517–528 (1990). https://doi.org/10.1007/BF02671924

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF02671924

Keywords

Search

Navigation