DEVELOPMENT AND RESEARCH OF THE AUTOMATIC CONTROL SYSTEM OF THE PROPERTIES OF THE NUCLEAR FUEL VVER-1000 FOR THE PROGRAM CONTROL THE POWER OF THE REACTOR WITH A CONSTANT AVERAGE COOLANT TEMPERATURE
Journal Title: Вчені записки Таврійського національного університету імені В. І. Вернадського. Серія: Технічні науки - Year 2018, Vol 29, Issue 6
Abstract
Today, all Ukrainian NPPs with VVER-1000 are operated in the mode of stabilizing the power of the power unit at a given level, although the equipment of the 1st circuit is designed for operation in the mode of maneuvering power. This is primarily due to the fact that at present, the maneuvering capacity of the reactor plant (RU) is carried out by operators in manual mode and only at the request of the dispatchers of the power system. Manual maneuvering by RP operators is very dangerous, since during control it is necessary to simultaneously control changes in many neutronic and technological parameters which leads to the need to take into account the human factor's influence on NPP safety. The solution to this problem can be the creation of ASR power unit, which will allow the unit to operate in power maneuvering mode with the requirement that the reliability and safety of the power unit are reduced, as well as the economic efficiency of the unit is kept at the required level.
Authors and Affiliations
Г. В. Андрощук, C. Н. Пелих
Keywords
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