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Nuclear Power Plants Based on Reactor Modules with SVBR-75/100

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Abstract

The basic results of the development of a design of a nuclear power plant with two 1600 MW(e) unit, each based on a lead–bismuth-cooled 100 MW(e) SVBR-75/100 fast reactor, are presented. A brief description is given of experience in using lead–bismuth coolant and the basic principles of the concept of the reactor system and its safety are presented, and substantiation is given for the modular structure of a power-generating unit. The basic stages in the adoption of modular-type nuclear power plants and other possible uses of SVBR-75/100 are examined.

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REFERENCES

  1. B. F. Gromov, O. G. Grigor'ev, A. V. Dedul', et al., “Analysis of operating experience of reactor systems with lead-bismuth coolant and accidents which have occurred,” in: Heavy Liquid-Metal Coolants in Nuclear Technologies. TZhMT-98, Obninsk (1999), Vol. 1, pp. 63-69.

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Authors and Affiliations

  1. State Science Center of the Russian Federation – A. I. Leipunskii Physics and Power Engineering Institute, Russia

    A. V. Zrodnikov, V. I. Chitaikin, G. I. Toshinskii & O. G. Grigor'ev

  2. Special Design Office Gidropress, Russia

    Yu. G. Dragunov, V. S. Stepanov & N. N. Klimov

  3. GNIPIKII Atoménergoproekt, Russia

    A. B. Malyshev, V. N. Krushel'nitskii & S. M. Takh

Authors
  1. A. V. Zrodnikov
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  2. V. I. Chitaikin
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  3. G. I. Toshinskii
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  4. O. G. Grigor'ev
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  5. Yu. G. Dragunov
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  6. V. S. Stepanov
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  7. N. N. Klimov
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  8. A. B. Malyshev
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  9. V. N. Krushel'nitskii
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  10. S. M. Takh
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Zrodnikov, A.V., Chitaikin, V.I., Toshinskii, G.I. et al. Nuclear Power Plants Based on Reactor Modules with SVBR-75/100. Atomic Energy 91, 957–966 (2001). https://doi.org/10.1023/A:1014862701400

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  • DOI: https://doi.org/10.1023/A:1014862701400

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