Výměník pro odvod zbytkového tepla jaderného reaktoru

Abstract

This bachelor thesis deals about structural design of barboteur of nuclear power plant. It is a special safety device of primary circuit, which regulates pressure of cooling water. Barboteur is a tank of 8,3 m length and diameter of 2,8 m filled to 2/3 by water. On first part of thesis are describe principle of function of primary circuit of nuclear power plant using pressurized water reactor VVER 440 and VVER 1000. On the next part of thesis are describe main parts of primary circuit. The practical part of bachelor thesis consists of design and calculation of parameters barboteur. Results of calculation are realised on 3D model of barboteur in sketching program Autodesk INVENTOR 2015. Then 3D model is transfer to the drawing documentation.

Description

Subject(s)

barboteur, reactor, pressuriser, nuclear power plant, steam, temperature, pressure

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