Abstract

Modern conditions for the development of nuclear energy in Russia impose maneuverability requirements on nuclear power plants. In particular, this is dictated by the energy development strategy of Russia for the period up to 2035, which sets the task of attracting nuclear power plants to participate in regulating the daily unevenness of the electrical load in the range of up to 50% of the rated power. In addition, nuclear power plants will be involved in the primary frequency regulation, which will oblige them to carry out unloading operation during the day. Since nuclear power plants in the power system always carry a base load, all these circumstances force us to look for ways to provide a base load. The traditional solution has been the use of pumped storage power plants (PSPP). But due to the specifics of their construction, the combination of nuclear power plants + pumped storage power plants is not effective. It is more effective to use a hydrogen complex based on the electrolysis of hydrogen and oxygen for the purpose of using them to overheat the working fluid in the steam turbine cycle of nuclear power plants during peak periods of electrical load in the power system. In this case, it is critically important to assess the rate of peak power release based on the criterion of the working life of the most important components of the turbine unit rotor - rotor blades and disks. In the article, based on well-known methods and models for fatigue wear, the working life of the working blades and disks of the first stage of the HPC rotor, as the most susceptible to cyclic wear, is assessed using the example of the C-1000-60/1500 turbine under conditions of using steam-hydrogen superheating of fresh steam.

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