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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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Steam generator heated with liquid sodium
Kóša, Štefan ; Bogdálek, Jan (referee) ; Šen, Hugo (advisor)
This bachelor’s thesis is concerned with engeneering a steam generator (secondary heat exchanger) for a fast breeder reactor. It includes proposal of the projected type, thermal, hydraulic and strenght calculation, and examination of a proposal in light of nuclear safety. It contains a lay-out of selected parts.
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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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The flange gasket modification of TC SVO1 ion filter manhole on the VVER 440 NPP
Šnajdárek, Ladislav ; Fiedler, Jan (referee) ; Šen, Hugo (advisor)
This diploma thesis is engaged in replacement of gasket ion filter used in the ion filter of continuous cleaning TC SV01 of rector coolant in nuclear power plants with VVER 440 reactor. Original nickel gasket is replaced by kammprofile gasket with expanded graphite. Calculation results are compared with each other and are described as suggestions for further calculation. The first part included a detailed description of the primary coolant water chemistry, along with a description of the function and structure of ion filter.
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Inovation components of EPR project
Martinek, Miroslav ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
The target of this work is to find innovative elements of EPR project. In the first part the paper deals with an introduction to the topic and explains water pressurized reactors. It describes the individual parts of the mechanism and their various types as well as their interconnection into a complete unit. The second part gives attention to innovations and modifications of EPR project in terms of location of buildings, reactor or safety requirements. The third part contains a simple calculation of a chosen mechanism.
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Heat exchanger design for closed gas turbine cycle
Sklenář, Oldřich ; Bogdálek, Jan (referee) ; Šen, Hugo (advisor)
This bachelor’s thesis deals with determination of parameters of an experimental high temperature gas-cooled nuclear reactor cycle and a project of a regenerative heat exchanger designed to this cycle. The first part is dedicated to thermal cycles. This part includes an actual summary of high temperature reactors, an analysis of their cycles, a theory of closed gas turbine cycle and a calculation of elected cycle. The second part concerns a review of heat exchangers and gas coolers used for nuclear energy purposes and heat transfer theory. The main objective of this part is a calculation of heat exchanger from the conceptual, thermal, hydraulic and strength point of view including inclusion of analysis of this solution.
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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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Heat exchangers Natrium - Carbon Dioxide
Foral, Štěpán ; Šimo, Tomáš (referee) ; Šen, Hugo (advisor)
This bachelor thesis describes design of heat exchanger for sodium cooled fast reactor of the IV. generation and compares the achieved solution with other realized projects. The first part deals with brief description of individual types of the nuclear reactors of the IV. generation and their main assets. There is an emphasis on the description of the sodium cooled fast nuclear reactor. The second part deals with complex design of a heat exchanger, when the initial concept is considered to be a heat exchanger with sodium on one side (warming medium) and carbon dioxide on the other side (heated medium). The core of this part is comparing individual concepts of the heat exchanger when variable construction materials are used. Furthermore there is accomplished range of heat, hydraulic and strength calculations of basic proportion of the options of the solution of the heat exchanger with work medium inside of pipes and outside of pipes. There are presented summary of the accomplished observation and comparing of the designed concept with realized similar projects in the conclusion.
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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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