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Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design

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Atomic Energy Aims and scope

The results of development work on and safety validation of high-density, low-enriched fuel for research nuclear reactors of Russian design are presented. Attention is focused mainly on the development of fuel assemblies with fuel based on UO2 + Al, U3Si2 + Al, and U9%Mo + Al for the LVR-15 research reactor (Czech Republic). A design-basis validation is given for IRT-4M fuel assemblies with fuel composition based on UO2 + Al and U3Si2 + Al, IRT-3M fuel assemblies with a fuel composition based on U9%Mo + Al, and IRT-P fuel assemblies with a fuel composition based on U3Si2 + Al and UO2 + Al. In substantiation of the operability and confirmation of the hydraulic characteristics of the IRT-P fuel assembly, which is equipped with 21 fuel rods, manufactured at NZKhK, there are plans to manufacture and conduct hydraulic testing of a full-scale model.

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References

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Authors and Affiliations

  1. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia

    Yu. S. Cherepnin, A. A. Pulinets, O. A. Kravtsova, A. R. Simonidi, E. S. Chizhova, I. A. Larionov & S. I. Logvenchev

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  1. Yu. S. Cherepnin
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  2. A. A. Pulinets
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  3. O. A. Kravtsova
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  4. A. R. Simonidi
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  5. E. S. Chizhova
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  6. I. A. Larionov
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  7. S. I. Logvenchev
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Corresponding author

Correspondence to E. S. Chizhova.

Additional information

Translated from Atomnaya Énergiya, Vol. 129, No. 4, pp. 231–233, October, 2020.

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Cherepnin, Y.S., Pulinets, A.A., Kravtsova, O.A. et al. Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design. At Energy 129, 234–236 (2021). https://doi.org/10.1007/s10512-021-00740-9

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  • DOI: https://doi.org/10.1007/s10512-021-00740-9

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