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Creep of uranium dioxide

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Soviet Atomic Energy Aims and scope

Conclusions

  1. 1.

    We have presented some experimental results relating to the creep of polycrystalline sintered UO2 over the temperature range 1600–1900°K for stresses of 0.4–4 kg/mm2.

  2. 2.

    The deformation of the UO2 samples during the tests leads to the formation of inhomogeneities and the development of cracks.

  3. 3.

    The average creep velocity depends linearly on stress at 1593°K. The minimum creep velocity may be satisfactorily described as a function of temperature and stress by Eq. (4).

  4. 4.

    When a neutron flux acts on the sample, the creep velocity increases and varies linearly with the fission density. For maximum fission densities of 0.625·1012 fissions/cm3·sec in the temperature range 1373–1523°K, and for stresses of 3 and 4 kg/mm2 in the sample, the creep velocity increases by a factor of three by comparison with laboratory tests.

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Authors
  1. Yu. V. Miloserdin
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  2. K. V. Naboichenko
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  3. I. S. Golovnin
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  4. Yu. K. Bibilashvili
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  5. T. S. Men'shikova
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  6. P. A. Mandryka
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  7. K. G. Bobkov
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  8. N. I. Arlamenkov
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  9. A. N. Bogatov
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  10. E. M. Minaev
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  11. L. S. Podval'nyi
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Additional information

Translated from Atomnaya Énergiya, Vol. 35, No. 6, pp. 371–375, December, 1973.

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Miloserdin, Y.V., Naboichenko, K.V., Golovnin, I.S. et al. Creep of uranium dioxide. At Energy 35, 1065–1069 (1973). https://doi.org/10.1007/BF01161882

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  • DOI: https://doi.org/10.1007/BF01161882

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