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Substantiation of the feasibility of using fuel rods with tungsten spraying in power fast reactors of new generation

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Abstract

The contemporary development of nuclear power technologies in Russia made it possible to create projects of economic and safe fast reactors of new generation. These reactors will be a basis of the large-scale nuclear power engineering in the middle and end of the 21st century. Fast reactors of inherent safety (BREST), in which heavy emergencies are deterministically excluded [1,2], are of most interest among such projects. However, the limits of domestic power engineering implemented in BREST projects are not completely reached; there are reserves for further bettering of the safety and, probably, efficiency of new generation reactors. There are 1 to 2 decades left for improving technologies of fast reactors of inherent safety. One of the BREST concept reserves—the usage of fuel-rod shells with tungsten spraying—is the idea unattractive and unrealistic at first sight due to the tungsten’s high cost and the large cross section of fast-neutron absorption. However, the performed analysis and the calculation studies make it possible to draw a conclusion on the potential possibility of using the tungsten coatings of fuel rods for further improvement of reliability and safety of BREST-type reactors without deterioration (and probably with improvement) of economical characteristics of nuclear power plants with these reactors.

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References

  1. V. V. Orlov, E. N. Avrorin, E. O. Adamov, et al., “Nontraditional Concepts of Nuclear Power Plants with Inherent Safety (New Nuclear Technology for the Next Stage Large-Scale Production of Nuclear Power),” At. Energ. 72(4), 317 (1992).

    Google Scholar 

  2. BREST-OD-300, Ed. by E. O. Adamov and V. V. Orlov, (Izd. FGUP NIKIET, Moscow, 2001) [in Russian]

    Google Scholar 

  3. http://www.atomic-energy.ru/node/9368.

  4. F. Ruhn, A. Adamantiades, J. Kantonn, and Ch. Brown, A Guide to Nuclear Power Technology (Wiley-Interscience, New York, 1984; Energoatomizdat, Moscow, 1989).

    Google Scholar 

  5. V. V. Kudinov, Application of Coatings by Spraying. Theory, Technology, and Equipment (Mashinostroenie, Moscow, 1993) [in Russian].

    Google Scholar 

  6. V. S. Okunev, “Influence of Isotope Composition of Coolant Based on Lead from Thorium Ores on Void Effect of Reactivity in BREST-Type Reactor,” Izv. Vuzov. Ser. Yadernaya Energetika, No. 2 (2006).

  7. L. V. Gurvich, G. V. Karachentsev, V. N. Kondrat’ev, et al., Energy of Breakup of Chemical Bonds. Ionization Potentials and Electron Affinity (Nauka, Moscow, 1974) [in Russian].

    Google Scholar 

  8. A. F. Prisevok, V. A. Fedortsev, A. I. Solovei, et al., RF Patent No. 2 009 027, Class of patent B22F7/04.

  9. MCNP-4C. Monte Carlo N-Particle Transport Code System (Oak Ridge National Laboratory, Radiation Safety Information Computational Center, RSICC CCC-700, 2000).

  10. V. S. Okunev, in Proceedings of MEPhI-2011 Scientific Session of MEPhI National Research Nuclear University (NIYaU MIFI, Moscow, 2010), Vol. 1, p. 59.

    Google Scholar 

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Original Russian Text © V.S. Okunev, 2011, published in Izvestiya RAN. Energetika.

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Okunev, V.S. Substantiation of the feasibility of using fuel rods with tungsten spraying in power fast reactors of new generation. Therm. Eng. 58, 1167–1171 (2011). https://doi.org/10.1134/S0040601511140060

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  • DOI: https://doi.org/10.1134/S0040601511140060

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