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Experimental investigation of single-stage control circuit of coolant outlet temperature in the bor-60 reactor

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Literature Cited

  1. Yu. E. Bagdasarov et al., Fast-Reactor Engineering [in Russian], Atomizdat, Moscow (1969).

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  2. V. I. Plyutinskii et al., in: Control of Nuclear Power Plants [in Russian], Vol. 2, Atomizdat, Moscow (1967), p. 5.

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  3. G. A. Karandashov and B. A. Kuvshinnikov, in: Control of Nuclear Power Plants [in Russian], Vol. 2, Atomizdat, Moscow (1969), p. 28.

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  4. A. I. Leipunskii et al., 4th Geneva Conference (1971), Report No. 750 (USSR).

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Authors
  1. V. A. Afanas'ev
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  2. V. M. Gryazev
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  3. V. N. Efimov
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Additional information

Translated from Atomnaya Énergiya, Vol. 34, No. 1, p. 30–31, January, 1973. Original article submitted December 30, 1972;

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Afanas'ev, V.A., Gryazev, V.M. & Efimov, V.N. Experimental investigation of single-stage control circuit of coolant outlet temperature in the bor-60 reactor. At Energy 34, 38–39 (1973). https://doi.org/10.1007/BF01404506

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  • DOI: https://doi.org/10.1007/BF01404506

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