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	The Intermediate Heat Exchanger for ESFR reactor primary circuit Švihel, Miroslav ; Baláš, Marek (referee) ; Šen, Hugo (advisor) The thesis is mainly focused on the design of the intermediate heat exchanger primary circuit of the reactor ESFR. Heat exchanger is calculated heat, hydraulic and strength and is finally processed part drawings. There are designed the basic dimensions of the tube bundle and container heat exchanger. There are included an overview of concepts and so far used types IHX at the nuclear power plants with fast reactors. There are also mentioned basic parameters of the project ESFR and evaluated the safety and operational reliability of the heat exchanger. Detailed record
	Tightness measurement of hermetic compartments in NPP Sklenár, Ondrej ; Martinec, Jiří (referee) ; Šen, Hugo (advisor) This diploma thesis deals with measuring the tightness of the hermetic area of nuclear power plant in the way of improving safety. Describes the layout and function of this area - the primary circuit of NPP with WWER 440/213 reactors, as well as methodology for leakage search and leakage calculation procedures. Personal contribution to the issue is a proposal improving tightness of the current state in hermetic area of NPP Jaslovské Bohunice – transition of jacketed pipe designed to collect water from the floor in the box of the steam generator to the heat exchanger of the shower system. This system belongs to the safety system designed to reduce pressure in the LOCA type of accident. Detailed record
	Change in the Production of oversize Components of the Pump Kratochvíl, Zdeněk ; Prokop, Jaroslav (referee) ; Kalivoda, Milan (advisor) The thesis proposes a method for implementing structural changes on the compression flange of the main circulation pump, at the time of its overhaul during the unit outage. This structural modification consists in Annular groove of the groove to a diameter of about 850 mm. It is necessary to choose a suitably radius of maximum made possible smoothly rounded grooves without notches to reduce the stress of the concentration at the corners of the groove. Possibilities for making this adjustment are considered in this thesis and then the technology is selected with control torque calculations. The selected technology consists in the sizing of grooves with the mobile numerically controlled machining lathe EFCO TDF-2 NC, which is documented in the Annular groove of the axial grooves. In conclusion there are described other possibilities of using of this mobile machine in the primary circuit of a nuclear power plant. Detailed record

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