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Leaktightness monitoring of the primary loop in steam generators at nuclear power stations using water-moderated water-cooled power reactor

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Soviet Atomic Energy Aims and scope

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Literature Cited

  1. M. I. Arsaev et al., Proc. SNIIP, Nuclear Instrumentation [in Russian], Atomizdat, Moscow (1970).

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  2. L. M. Luzanova and B. G. Pologikh, Symposium on Planning Measures to Cope with Radiation Accidents, Vienna (1969), paper Sm119/44.

  3. E. Smith et al., Trans. Amer. Nucl. Soc.,11, No. 1, 371 (1968).

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  4. Rockwell (editor), Nuclear Reactor Shielding [Russian translation], Izd-vo Inostr. Lit (1958).

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Authors
  1. T. K. Fedchenko
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  2. A. A. Il'khman
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Additional information

Translated from Atomnaya Énergiya, Vol. 34, No. 1, pp. 39–40, January, 1973.

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Fedchenko, T.K., Il'khman, A.A. Leaktightness monitoring of the primary loop in steam generators at nuclear power stations using water-moderated water-cooled power reactor. At Energy 34, 49–51 (1973). https://doi.org/10.1007/BF01404516

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  • DOI: https://doi.org/10.1007/BF01404516

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