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Results of U0.55Pu0.45N and U0.4Pu0.6N mixed mononitride fuel tests in a bor-60 reactor to burnup 12% h.a.

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The results of post-reactor studies of U0.55Pu0.45N and U0.4Pu0.6N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively, with power density 430 and 540 W/cm. All fuel elements remained hermetic; the ChS-68 steel cladding (20% cold deformation) retained excess plasticity. The maximum zone of interaction between the cladding and the fuel and fission products did not exceed 15 μm. The swelling rate of U0.4Pu0.6N and U0.55Pu0.45N fuel was 1.1 and 0.68%/% burnup, respectively. The gas release did not exceed 19.3 and 19%. The steel damage dose was 43 dpa. The character of the porosity distribution in the fuel affects the swelling and gas release.

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Authors and Affiliations

  1. Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM), Moscow, Russia

    B. D. Rogozkin, N. M. Stepennova, Yu. E. Fedorov & M. G. Shishkov

  2. State Science Center – Research Institute for Atomic Reactors (GNTs NIIAR), Dimitrovgrad, Russia

    F. N. Kryukov, S. V. Kuzmin, O. N. Nikitin & A. V. Belyaeva

  3. State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (GNTs RF – FEI), Obninsk, Russia

    L. M. Zabudko

Authors
  1. B. D. Rogozkin
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  2. N. M. Stepennova
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  3. Yu. E. Fedorov
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  4. M. G. Shishkov
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  5. F. N. Kryukov
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  6. S. V. Kuzmin
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  7. O. N. Nikitin
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  8. A. V. Belyaeva
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  9. L. M. Zabudko
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Translated from Atomnaya Énergiya,Vol. 110, No. 6, pp. 332–346, June, 2011.

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Rogozkin, B.D., Stepennova, N.M., Fedorov, Y.E. et al. Results of U0.55Pu0.45N and U0.4Pu0.6N mixed mononitride fuel tests in a bor-60 reactor to burnup 12% h.a.. At Energy 110, 412–429 (2011). https://doi.org/10.1007/s10512-011-9442-0

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  • DOI: https://doi.org/10.1007/s10512-011-9442-0

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