Operational studies of the thermohydraulic characteristics of steam generators in a BN-600 power-generating unit

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[1] Sheinkman, A.G.
[2] Bel'tyukov, A.I.
[3] Vylomov, V.V.
[4] Karpenko, A.I.
[5] Lyzhin, A.A.
[6] Smirnov, M.V.
[7] Khaletskii, E.E.
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Sheinkman, A.G. | 1600年 / 36期
关键词：
Nuclear Reactors; Liquid Metal Cooled;
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