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The capacities of a corrosion-fatigue monitoring system in managing the service life of steam generators operating at nuclear power stations equipped with a VVER-1000M reactor

G.F. Banyuk, O. P. Arkhipov, S.I. Brykov, Yu. V. Kharitonov, В. Г. Крицкий, I. G. Berezina, Mikhail Sofin

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Abstract

We consider the possibilities of using a corrosion-fatigue monitoring system for operatively monitoring the corrosion of heat-transfer tubes in steam generators operating at nuclear power stations equipped with VVER reactors. It is proposed that this system be tested on a power unit built around a VVER-1000 reactor.

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What this paper is about

We consider the possibilities of using a corrosion-fatigue monitoring system for operatively monitoring the corrosion of heat-transfer tubes in steam generators operating at nuclear power stations equipped with VVER reactors. It is proposed that this system be tested on a power unit built around a VVER-1000 reactor.

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Available abstract

We consider the possibilities of using a corrosion-fatigue monitoring system for operatively monitoring the corrosion of heat-transfer tubes in steam generators operating at nuclear power stations equipped with VVER reactors. It is proposed that this system be tested on a power unit built around a VVER-1000 reactor.

Key concepts: VVER, Nuclear engineering, Nuclear power, Pressurized water reactor, Service life, Corrosion, Nuclear power plant, Nuclear reactor

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The capacities of a corrosion-fatigue monitoring system in managing the service life of steam generators operating at nuclear power stations equipped with a VVER-1000M reactor — Research Paper | ScholarLens