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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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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.
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Energy conversion systems for nuclear power plants with soduim fast reactor (SFR)
Netopilová, Petra ; Šen, Hugo (referee) ; Matal, Oldřich (advisor)
The aim of the dissertation is proposing and solving energy convection systems for nuc-lear power plants with a sodium fast reactor of the 4th generation. The first part of the dissertation deals with collection and evaluation of information available about nuclear power plants with sodium fast reactor which use nuclear or non-nuclear reheating to increase thermal efficiency. On the basis of the acquired information, thermal schemes are developed and thermal effi-ciency is determined for the systems working in both Rankine thermal cycle and Brayton thermal cycle. In the further part of the dissertation thermal calculation of the reheater for nuclear and non-nuclear reheating is made for the systems working in Rankine thermal cycle. At the end of this dissertation, an apparatus suitable for these systems is suggested and the systems are evaluated in terms of technical implementation and nuclear safety.
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Trasfer Heat Analysis in Steam Generators in blocks of VVER 440
Roupec, Petr ; Pulec, Jiří (referee) ; Šen, Hugo (advisor)
The aim of this thesis is to analyze the heat transfer in steam generator of blocks in the nuclear power plant VVER 440. The steam generator represents the border between the primary and the secondary circuit. The heat is carried from a warm water from reactor to a cold water. The steam arises after the heat transfer and drives the steam turbine. An important quantity which represents the heat transfer is a heat transfer factor. This thesis is divided into theoretical and a practical part. In the theoretical part is mentioned a principle of the steam generator and the theoretical calculation of the heat transfer factor, which comes first of all from the character of the streaming in the steam generator. The practical part brings a comparison of the heat transfer factor calculated from data measured after the start of the third block of EDU in 1986, with the heat transfer factor which comes from the measurement after the power-increase for 105 % of nominal power of the same block in 2009. Further is shown the prediction of the heat transfer factor for next power-increase and the following service is shown too.
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Fluid flow modeling in rotating engines
Joch, Lukáš ; Šen, Hugo (referee) ; Pospíšil, Jiří (advisor)
This thesis deals with modelling of flow in rotating engines. The introduction of the thesis discusses the principles of CFD modelling, such as mathematical flow model, numerical solution methods and model of turbulence. Next, the thesis is engaged in possibilities of a calculation model creation and its setting for a used model of steam turbine regulatory stage. The last part contains evaluation of calculation models and their comparison with different input parameters, regarding the fact that the aim is to get the most suitable setting for reaching the peak efficiency.
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Thermal cycles optimization
Voseček, Petr ; Šen, Hugo (referee) ; Fiedler, Jan (advisor)
The main goal of the thesis was a selection of appropriate thermal cycles for the considerated nuclear power stations with the Generation IV reactors. Characterization and specification of the parametres of the Brayton and the Rankine-Clausi thermodynamic cycle, their optimalization with regard to the parametres of the first cycle was made, than analysis of cycles´properties, mostly efficiency, output and process layout.
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Evaluation of power and coolant flow in reactor core
Tvrdý, Miloslav ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
This graduation thesis deals with evaluation of power and coolant flow in reactor core. The first part is a description of nuclear power plant VVER 440. It is focused on parts important for transfer and utilize energy in regular operating of generating block. In the second part, the equations for calculation of power and coolant flow in reactor core are deduced. The last part is about designing the program for calculation of published values. There are specified requirements for the program and on the basis of this the source code is written. The parts of code are described. In conclusion of this part, the user's manual is work out. The program is on CD in the annexe.
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Energy balance of biomass heating plant
Žmolík, Václav ; Šen, Hugo (referee) ; Baláš, Marek (advisor)
This thesis deals with a design of a biomass heating plant combinating a Rankin-Clausius cyklus and a CHP unit. The CHP unit fuel is a biogas and the boiler fuel is a wooden chip. The adapted CHP unit regenerates feed-water of the R-C cycles. This design is technicaly and economicalty compared with the Rankin-Clausius cycle without feed-water regeneration by the CHP unit.
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Steam generator for nuclear power plant with fast reactor
Karička, Radoslav ; Nesvadba, Lukáš (referee) ; Šen, Hugo (advisor)
The aim of the project is to design a steam generator in which the sodium flows pipeline hand, and on the other hand, water flow and water vapor (H2O). The main idea of this thesis is to propose such a steam generator, to avoid or eliminate the possibility of adverse reactions of sodium with water and, if this phenomenon occurs, thus minimizing the damage caused by this reaction. The work contains information on the implementation of steam, steam option, the necessary calculations for the design and construction and evaluation.
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Gas turbine closed cycle
Kovář, Radim ; Šen, Hugo (referee) ; Fiedler, Jan (advisor)
Diploma thesis deals with the gas turbine closed cycle. The first part concerns the maximum of theoretical efficiency and practical excutable efficiency for the cycles without regeneration, cycles with regeneration and cycles with regeneration with split compression. The second part concerns the optimalization of the recuperator towards the speed of gas flow in the pipes of the recuperator. The third part includes weight and size design of two kinds of recuperators for different levels of regeneration.
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