The particulars of the design of new-generation ASCTP and experience in implementing the system in the No. 3 unit of the Kalininskaya nuclear power plant are examined. The basic requirements and the main approaches for developing ASCTP for the power-generating units of nuclear power plants with newgeneration VVER, including protection from failures for general reasons in the safety control systems, expansion of the functions of the system of the top block level, intellectually signaling, automation level of technological processes, and servicing of the means of automation are presented. It is noted that the principle of optimizing the application of modern information technologies taking account of experience in design and operation of power-generating units with mandatory maintenance of the updated base must play an important role in determining the requirements for and making technical decisions concerning ASCTP for new-generation VVER. The strategy of our country's energy policy is oriented toward accelerated development of nuclear power plant capacity, increasing the power and service life of operating power-generating units, building and commissioning new-generation units with the AES-2006 design at the Novovoronezh and Leningradskaya nuclear power plants -VVER-1200.The systems controlling a nuclear power plant (automated systems for controlling a technological process -ASCTP) must be improved using modern information technologies, which is an important strategic part of the design, in order to make technological objects as complex as the power-generating units of nuclear power plants safer and more efficientThe AES-2006 ASCTP design is based on technical solutions incorporated in domestic and foreign units in Russian built nuclear power plants -the No. 3 unit of the Kalininskaya nuclear power plant, Tian Wan nuclear power plant (China), the nuclear power plant in Bushehr (Iran), the Kundankulam nuclear power plant (India) -as well as world trends and requirements.ASCTP for the No. 3 Unit of the Kalininskaya Nuclear Power Plant. During the completion of this powergenerating unit (design of a serially produced power-generating unit with VVER-1000 with a V-320 reactor facility and K-1000/60-3000 turbo facility) a decision was made to develop and adopt a new-generation ASCTP.
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