Development of Supercritical-Water Cooled Reactors in Russia and Abroad

Analysis of foreign research on SCWR attests to their systemacy and consistency and, especially, the timely training of cadres. The knowledge accumulated in our country in the last 10 years makes it possible to refine the previously developed concept of the 1700 MW(e) VVER-SKD reactor, indicate a plan for top-priority research, formulate a technical mission and proceed to the design of an experimental 30 MW reactor.

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Correspondence to A. P. Glebov or A. V. Klushin.

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Translated from Atomnaya Énergiya, Vol. 116, No. 5, pp. 267–274, May, 2014.

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Glebov, A.P., Klushin, A.V. Development of Supercritical-Water Cooled Reactors in Russia and Abroad. At Energy 116, 320–329 (2014). https://doi.org/10.1007/s10512-014-9860-x

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Keywords

  • Plutonium
  • Fuel Element
  • Fuel Assembly
  • Peripheral Zone
  • Neutron Spectrum