Skip to main content
Log in

Additional mechanisms of accelerated gas release from uranium fuel under accident conditions

  • Articles
  • Published:
Atomic Energy Aims and scope

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

Access this article

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

Instant access to the full article PDF.

Literature Cited

  1. J. Turnbull and C. Friskney, “The relation between microstructure and the release of unstable fission products during high temperature irradiation of UO2,” J. Nucl. Mater.,71, 238 (1978).

    Google Scholar 

  2. H. Zimmerman, “Investigation of swelling and fission gas behavior in uranium dioxide,” ibid.,75, 154–161 (1978).

  3. M. Osborn, J. Collins, R. Lorenz, and R. Strain, “Fission product release and fuel behavior in tests of LWR fuel under accident conditions,” in: Proceedings of International Symposium on Source Term Evaluation for Accident Conditions, 89–104 (1985).

  4. A. F. Efros, Physics and Geometry of Disorder Nauka [in Russian], Moscow (1982).

  5. J. Essam, in: Phase Transitions and Critical Phenomena, Vol. 2, edited by C. Domb and M. Green, Academic Press, New York (1972), p. 197.

    Google Scholar 

  6. G. Small, Rep. AERE R-12803 (1988).

  7. G. Small, Rep. AERE R-12956 (1988).

  8. F. Nichols, “Coalescence of two spheres by surface diffusion,” J. Appl. Phys.,37, No. 7, 2805–2808 (1966).

    Google Scholar 

  9. F. Nichols and W. Mullins, Trans. AIME,233, No. 10, 1840 (1965).

    Google Scholar 

  10. M. Smoluchowski, Z. Physik. Chem.,92, 129 (1917).

    Google Scholar 

  11. C. Baker, “The fission gas bubble distribution in uranium dioxide from high temperature irradiated SGHWR fuel pins,” J. Nucl. Mater.,66, 129 (1917).

    Google Scholar 

  12. M. Osborn, R. Lorenz, and J. Travis, Data Summary Report for Fission Product Release Test VI-5 NUREG/CR-5668 (1991).

  13. M. Hutchings, “High-temperature studies of UO2 and ThO2 using neutron scattering techniques,” J. Chem. Soc. Farad. Trans. 2,83, No. 7, 1083–1103 (1987).

    Google Scholar 

  14. H. Matzke, “Atomic transport properties of UO2 and mixed oxides (U, Pu)O2,” ibid., 1121–1142.

  15. E. Randklev and C. Hisman, in: Fast Breeder Reactor Fuel Performance, edited by E. Norman, Am. Nucl. Soc., US DOE, 406 (1979).

  16. J. Rest, D. Osetek, and J. Hartwell, “Isotopic fission product release from nuclear fuel under severe core damage accident conditions,” in: Proceedings of International Symposium on Source Term Evaluation for Accident Conditions (1985), pp. 105–118.

  17. J. Rest, “The coupled kinetics of grain growth and fission product behavior in nuclear fuel under degraded-core accident conditions,” J. Nucl. Mater.,131, 291–302 (1985).

    Google Scholar 

Download references

Authors

Additional information

IBRAE Russian Academy of Sciences. Translated from Atomnaya Énergiya, Vol. 74, No. 5, pp. 382–387, May, 1993.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Veshchunov, M.S., Galimov, R.R. Additional mechanisms of accelerated gas release from uranium fuel under accident conditions. At Energy 74, 348–352 (1993). https://doi.org/10.1007/BF00844619

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF00844619

Keywords

Navigation