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Reactor Tests of High-Temperature Gas-Cooled Fuel Rods

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Atomic Energy Aims and scope

Tests of the fuel rods of a high-temperature gas-cooled reactor were performed in the loop installation of the MIR.M1 reactor. General information about the objectives of the experiment and the modernized loop installation is presented. The designs of the loop channel, experimental fuel assembly, and fuel rods, including the thermometric versions, are described. The main results of post-reactor studies and a general analysis of the results are presented.

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References

  1. Yu. G. Dragunov, B. A. Gabaraev, V. V. Uzhanova, et al., “Results of the development of reactor installation for the Prometheus spacecraft,” Probl. Mashinostr. Avtomatiz., No. 4, 118–128 (2014).

  2. Yu. G. Dragunov, “Fast gas-cooled reactor for a megawatt space nuclear energy and propulsion installation,” in: 3rd Int. Sci. Tech. Conf. on Innovative Projects and Technologies of Nuclear Energy (MNTK NIKIET-2014), NIKIET, Moscow, Oct. 7–10, 2014, Vol. 1, pp. 21–25.

  3. I. Kh. Merkurisov, A. E. Rusanov, A. L. Izhutov, Yu. S. Cherepnin, “Irradiation devices for high-temperature reactor tests of core elements,” ibid, pp. 357–367.

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Authors and Affiliations

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

    S. Yu. Bulkin, R. S. Kuz’menko, D. Yu. Loginov, E. L. Romadova, Yu. S. Cherepnin & K. I. Shut’ko

  2. State Science Center of the Russian Federation – Research Institute of Atomic Reactors (SSC RIAR), Dimitrovgrad, Russia

    A. L. Izhutov

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

    I. Kh. Merkurisov

Authors
  1. S. Yu. Bulkin
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  2. R. S. Kuz’menko
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  3. D. Yu. Loginov
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  4. E. L. Romadova
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  5. Yu. S. Cherepnin
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  6. K. I. Shut’ko
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  7. A. L. Izhutov
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  8. I. Kh. Merkurisov
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Corresponding author

Correspondence to D. Yu. Loginov.

Additional information

Translated from Atomnaya Énergiya, Vol. 129, No. 5, pp. 247–248, November, 2020.

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Bulkin, S.Y., Kuz’menko, R.S., Loginov, D.Y. et al. Reactor Tests of High-Temperature Gas-Cooled Fuel Rods. At Energy 129, 248–250 (2021). https://doi.org/10.1007/s10512-021-00743-6

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  • DOI: https://doi.org/10.1007/s10512-021-00743-6

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