Investigation of the random component of the heat-release distribution in a nuclear reactor-Reference-Cited by-同舟云学术

Investigation of the random component of the heat-release distribution in a nuclear reactor

Published:1976-06 Issue:6 Volume:40 Page:546-550
ISSN:0038-531X
Container-title:Soviet Atomic Energy
language:en
Short-container-title:At Energy

Author:

Karpov V. A.,Nazaryan V. G.,Postnikov V. V.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering,General Engineering,Nuclear Energy and Engineering

Link

http://link.springer.com/content/pdf/10.1007/BF01126954.pdf

Reference5 articles.

1. I. Ya. Emel'yanov et al., At. Énerg.,34, No. 2, 75 (1973).

2. I. Ya. Emel'yanov et al., At. Énerg.,29, No. 4, 298 (1970).

3. V. A. Karpov, in: Collection of Reports on the Programs and Methods of Calculating Nuclear Reactors [in Russian], Izd. CMEA, Dimitrovgrad (1975), p. 89.

4. I. Ya. Emel'yanov et al., in: Experience in the Operation of Nuclear Power Stations and Paths for the Further Development of Nuclear Power Generation [in Russian], Vol. 1, Izd. FÉI, Obninsk (1974), p. 81.

5. I. Ya. Emel'yanov et al., Report on the Conference of Mutual Economic Aid Countries on Methods of Monitoring and Controlling Nuclear Reactors and Nuclear Power Stations [in Russian], Warsaw (1973).

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