Search Results - "Korol’kov, B. M."

Development, construction, and use of pneumometric tubes for measurement of steam flow in the steam lines of PVG-1000 at NPP by Gorbunov, Yu. S., Ageev, A. G., Vasil’eva, R. V., Korol’kov, B. M.

“…A system for the direct measurement of steam flow in steam lines after a steam generator, which utilizes a special design of pneumometric tubes and a computing…”
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Determination of the Flow Rate of Coolant in Pipelines with Unstabilized Flow of Fluid in the Area Following a Bend by Boltenko, É. A., Davydov, M. V., Korol’kov, B. M., Basov, A. V., Kononenko, I. V., Sharov, V. P.

“…Questions related to the determination of the flow rate of coolant in the pipelines of electric plants are considered. Amethod of determining the flow of…”
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Vapor content of boiling coolant in tube and rod assemblies by Soziev, R. I., Korol'kov, B. M.

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Experimental Substantiation, Testing, and Commissioning of a Novel Separation System for Steam Generators of Nuclear Power Plants with VVER-1000 Reactors by Nigmatulin, B. I., Ageev, A. G., Blinkov, V. N., Vasil'eva, R. V., Korol'kov, B. M., Dragunov, Yu. G., Trunov, N. B., Nekrasov, A. V., Ilyushin, V. F.

“…The separation system of a PGV-1000 steam generator is modernized on the basis of bench tests of model PGV-1000 steam generators, full-scale tests of steam…”
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