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Radiation damage of VVER-440 based Dukovany NPP reactor pressure vessel investigation
Říha, Tomáš ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This master‘s thesis deals with radiation damage of reactor pressure vessels, specifically of NPP Dukovany Unit No. 3. In general damage mechanisms of reactor steels are described and possibilities of monitoring of material degradation and its recovery used at NPP’s all over the world are mentioned as well. A practical part of the thesis is focused on interpretation of analyses carried out with the assistance of MOBY DICK code. The ground of these analyses is a neutron fluence value development on different locations of RPV for the whole life of operation up to 24th cycle. The analyses results are put into context with performed in-service inspections. The thesis follows up with neutron fluence computation for the future cycles containing new types of nuclear fuel up to 34th cycle. The outcome of practical part of the master‘s thesis is a comparison between new types of nuclear fuel with respect to radiation damage of RPV’s.
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Temperature field analysis of spent fuel cask
Švaříček, Tomáš ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
The purpose of this thesis is temperature field analysis of spent fuel cask destined for dry buffer storage. Also to show possible ways of solving the difficulties in temperature field analysis, together with definition of simplifying presumptions and boundary conditions. Based on reasonable arguments were designed solving formulas, gained analytic solution of the temperature field and then compare analytical solution with numeric solution from ANSYS in the end of thesis.
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The flange gasket modification of VVER 1000 pressurizer manhole
Švaříček, Tomáš ; Fiedler, Jan (referee) ; Šen, Hugo (advisor)
The main purpose of this thesis is the modification of the original flange gasket of the VVER1000 pressurizer manhole. Then the construction and function of the pressurizer itself is described, together with detailed calculations of the original and new modified gasket to meet the ČSN EN 1591 standard together with a description of the legislation that has to be followed in the calculations. The comparisons of both gasket types together with main conclusions are placed in the last section of this thesis.
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Intermediate heat exchanger natrium - natrium
Kupčík, Petr ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This paper deals with intermediate heat exchangers in nuclear power plants. First section of this paper is devoted to analysis and divide of construction designs of intermediate heat exchangers in commercial and experimental power plants. There is a description of thermal, hydraulic and strength calculations during projection of IHX in the second chapter. There has been made a blueprint of loop type IHX in the final chapter of this paper.
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The flange gasket modification of SG VVER 440 primary collector
Blažková, Eva ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
The aim of this thesis is to address issues concerning the sealing of the lid for the primary collector within the steam generator (SG) of the nuclear power plant VVER 440. These steam generators are sealed in the original design by nickel rings. Modifying the existing method of sealing by a new type of sealing material, primarily from expanded graphite, can significantly reduce the pressure in the sealing surface and also stress in bolts and flanged joints. The new solution of sealing between the joint of collector and the lid should extend the life of joints and thus the nuclear and technical safety. The text is divided into the theoretical and computational part. A principle of the SG, the SG design, and a description of the joint and lid are mentioned in the theoretical part. The computational part shows calculations of the new joint, the original one, and comparison of both solutions in terms of technical and nuclear safety. The work contains drawing of the new joint.
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Upgrading the secondary circuit of the Dukovany NPP
Fialová, Michaela ; Fiedler, Jan (referee) ; Šen, Hugo (advisor)
With the ever increasing usage of electric power and decreasing supply of natural resources, there is a growing effort to effectivelly maximise current dispositions of resources. Utilising project reserves at already functioning Nuclear powerplants belongs to these projects. In this article I am going to describe this utilisation and overall modernisation of the Dukovany Nuclear powerplant.
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A fuel cell, as an alternative source of electricity
Kürthy, Marián ; Šen, Hugo (referee) ; Pospíšil, Jiří (advisor)
The work deals with fuel cell technology, the principle of fuel cells and their division. Also there is presented an option of natural gas utilization as a fuel for fuel cells in this work. In the end of this work two scenarios of fuel cell usage in microcogeneration are introduced and there is also a technical economic evaluation of fuel cell microcogeneration unit used in these scenarios.
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The steam generator for ESFR reactor
Bátěk, David ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This master thesis deals steam generator for ESFR (European Sodium Fast Reactor), which is heated by liquid sodium. In the beginning chapters, there are theoretic information about ESFR's parameters and its' comparison with ohter types of heat exchangers in nuclear reactors with the same principal (sodium as a coolant). Then designing part follows, which contents of introduction of calculations, option of material and conception of heater. Computational part on its own includes thermal, hydraulic and stress calculations and comparison with aspects in nuclear safety and security.
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Fuel elements thermal field analysis
Vacek, Jiří ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
The purpose of this thesis is to describe calculation procedures of fuel element thermal field analysis. The next is VVER-440 fuel element solution for selected operating conditions. These solutions are also made numerically with ANSYS. The importance of each effect on solution is assessed in thesis. The possibilities of some simplifications are also assessed.
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The feedwater safety valve flow capacity analysis
Fialová, Michaela ; Lisý, Martin (referee) ; Šen, Hugo (advisor)
In this thesis I review the sufficient flow capacity of the safety valve against high-pressure heater thermal pressurization in high-pressure feedwater heater on nuclear power Dukovany. I present basic possible cases of thermal pressurization both a high node heater, and the extended pressure unit in case of closure all power heads to steam generators.
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