Návrh vodorovného parního generátoru pro jadernou elektrárnu VVER 640

Abstract

This diploma thesis deals with the design of the horizontal steam generator for nuclear power plant - type VVER 640. The theoretical part describes the primary circuit of the nuclear power plant and the development of different types of blocks of VVER. The thesis particularly focuses on the properties of the steam generator (SG) and its function in the circuit of a nuclear power plant.

Based on the given parameters, the thermal calculation of SG was made to ascertain the heat transfer surface and the length of the heat pipes. Furthermore, the project deals with the possible materials and strength check of individual segments of the steam generator. Pressure loss of the primary circuit SG was ascertained by the hydraulic calculation. The thesis furthermore suggests the design of the equipment which removes moisture from the produced steam.