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Fuel of nuclear reactors and fuel cycle
Bátěk, David ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This bachelor thesis describes nuclear fuels used in today's nuclear reactors as well as parts of fuel cycle, which includes all activities like uranium mining and prepairing, energy utilization and storage at the end of a cycle. There are also information about world production of uranium and posibilities of manipulation with used nuclear fuel, including transmutation technologies.
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Review of world nuclear reactors
Blažková, Eva ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This bachelor work is focused on creating an overview of nuclear reactor types, their categorization and engineering approach to particular designs. Furthermore, it also lists countries having nuclear reactors in possession and their standpoint towards nuclear energy in general. A brief summary of the third and fourth generation and their future energy potential is included as well. This work primarily reflects present-day status.
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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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Ways of radioactive materials saving in the Czech Republic and in the world
Polák, Luboš ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
Management of spent nuclear fuel and radioactive waste are many. The aim of this thesis was to summarize the attitude of the Czech Republic and the other major countries on this issue. First is given the classification of radioactive waste according to various criteria. Consequently, it is defined and described the fuel cycle, as the largest producer of all types of radioactive waste. Then is analyzed approach of the Czech Republic to the management of all type radioactive waste and the attitude to deep geological repository. At the end are some, in this respect, major countries and their attitude to deal with spent nuclear fuel, radioactive waste and the method of final disposal.
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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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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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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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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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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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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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