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LiF-NaF-KF Coolant Phase Diagram
Mikula, Hynek ; Matal, Oldřich (advisor)
In introduction this graduation theses discource about phase diagrams and thein fission. Next part is about concrete phase diagrams NaF – KF, NaF – LiF, KF – LiF. Their determination trough use of cooling surves and their specification trough use of numerical method. Conclusion contains proposal of method for concrete phase diagram of NaF – KF – LiF.
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Approach to the nuclaer safety of the 3rd generation nuclear reactors
Pavlíček, Michal ; Kolář, Jaroslav (referee) ; Kolář, Jaroslav (referee) ; Matal, Oldřich (advisor)
The main target of the master´s thesis is reviewing the generation III nuclear reactors in term of the nuclear safety. At first we have to learn some theory of the nuclear safety in order to understand safety systems of the generation III nuclear reactors. Therefore the thesis is divided into two parts. Legislative and technical approaches to nuclear safety are mentioned in the first part. Regulatory bodies, whose task is to supervise nuclear safety in the nuclear power plants, belongs to the legislative approaches. There are defined terms such as defence in depth, redundancy, diversity, etc. There are mentioned methods to assessing nuclear safety – deterministic and probabilistic methods, especially probabilistic methods, for which a simple example is provided. There are also mentioned active and passive safety systems and their significance for nuclear safety and inherent safety too. There is an example of the function of the active and passive safety systems of the EDU nuclear power plant in conclusion of this issue. The second part deals with description of the selected nuclear reactors in context of the construction of the new units of nuclear power plant in Temelín. The nuclear reactors from companies, which applied for the public tender opened by ČEZ, a. s., for the construction of the ETE 3+4. Thus, the nuclear reactor MIR-1200 by ATOMSTROYEXPORT (Russian Federation), the nuclear reactor AP1000 by WESTINGHOUSE (USA) and the nuclear reactor EPR by AREVA (France) are taken into account . Comparison of the generation II and these generation III+ nuclear reactors necessarily belongs to this master´s thesis. These the generation III+ nuclear reactors are compared with the nuclear reactor VVER 440 (EDU) and in particular with the nuclear reactor VVER 1000, which is operated in the nuclear power plant Temelín. The final chapter contains generally appraisal of the whole problem.
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Seal design MDP MCP 317 for Paks NPP
Svoboda, Pavel ; Šimo, Tomáš (referee) ; Matal, Oldřich (advisor)
This diploma work is engaged in replacement of gasket main dividing plane of reactor coolant pumps in nuclear power plant Paks. Of the newly suggested gasket is kammprofile gasket with expanded graphite layer. This work contain suggestion and calculation of new sealing a knot and calculation existing sealing the knot. Results are confrontacion and sequentially is discussed influence on main dividing plane HCČ 317 by use the new and the existing gasket. In this work is contained description brief of legislation. This legislation must keep by design components dedicated for nuclear equipment. Next this work contain view of the most important sealing knots used in primary system of Nuclear Power Plant type VVER 440.
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Analysis of possibilities for use of III. and IV. generation of nuclear reactors for the Czech Republic
Gajdzica, Lukáš ; Kopřiva, Radek (referee) ; Kopřiva, Radek (referee) ; Matal, Oldřich (advisor)
The thesis deals with the analysis of possibilities for use of III. and IV. generation of nuclear reactors for the Czech Republic. Introduction deals with basic principles of nuclear energetics and fuel cycle which is closely associated with the issue and its development and application in practice will have a significant effect both for choice of future types of nuclear reactors of IV. generation and the matter of settlement with spent nuclear fuel. In other parts the thesis deals with the present state of nuclear energetics in the Czech Republic, compares concrete chosen types of nuclear power plants of III. generation and generally describes nuclear reactors and power plants of IV. generation. Final part of the work is focused on questions concerning the possibility of construction of new blocks of nuclear power plants in the Czech Republic and presents concrete recommendation from author´s point of view.
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Sodium - Carbon-dioxide Heat Exchangers for Sodium Cooled Fast Reactor NPP (SFR)
Foral, Štěpán ; Šimo, Tomáš (referee) ; Matal, Oldřich (advisor)
This master’s thesis deals with a design of Na-CO2 heat exchanger. There is a comparison of shell and tube heat exchanger with PCHE in the first part. Further the shell and tube heat exchanger with internally finned tubes was chosen as the basic conception. There was performed an optimization of construct and operations parameters for this concept. The optimization was performed on the basis of thermal and hydraulic calculations. Further there were performed calculations for ensuring of safe operation of the heat exchanger. The conclusion of the diploma thesis deals with comparison of the designed heat exchanger with similar projects.
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Steam generator module
Kaláb, Ctibor ; Šimo, Tomáš (referee) ; Matal, Oldřich (advisor)
The thesis deals with a project of a steam generator heated with liquid sodium. The first section describes some types of steam generators at nuclear power plants which have been projected or put into use. The next part presents a draft concept of the steam generator, solved by this work. The implementation of the steam generator module has been selected from several options, based on the thermal, hydraulic and stress calculations and on the chosen criteria. The conclusion of this thesis deals with the evaluation of the final solution in terms of nuclear safety and technical solutions, and compares this solution to similar projects following various criteria.
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Determining the life storage of a carbon steel cask
Klimek, Stanislav ; Slovák, Jiří (referee) ; Matal, Oldřich (advisor)
Author´s name: Bc. Stanislav Klimek School: Brno University of Technology, Faculty of Mechanical Engineering, Energy institute Title: Determining the life storage of a carbon steel cask Consultant: Prof. Ing. Oldřich Matal, CSc. Number of pages: 70 Year: 2009 The assignment of this diploma thesis is to estimate the lifetime of spent fuel container made from carbon steel grade. This container is designed for deep geological disposal of spent nuclear fuel. Basic mechanism of corrosion are described in detail in the first part. Further on, this work deals with the other specific phenomena and influences, which affect at corrosion of steel in conditions of a deep geological repository. Heat, radiation and surroundings are considered of particular importance. In the following part an estimate of the lifetime of model container is introduced, which is affected by temperature and radiation. Here recommendations for protection of container are introduced, arising from the model calculation. Finally, the relevancy of incidence of particular parameters is evaluated, which affect the corrosion.
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The Nuclear Power Plant – The Green Source of Energy
Hynčica, Martin ; Vágner, Jiří (referee) ; Vágner, Jiří (referee) ; Matal, Oldřich (advisor)
This diploma thesis deals with nuclear energetics and its impact to the environment. Present state of the energetics, mainly nuclear energetics, in the Czech Republic is discussed here. Also perspective of nuclear energetics is given. The thesis describes nuclear power plant waste handling and also spent nuclear fuel handling. Nuclear power plant is compared with other sources of electric energy, which are counted to the energetic mix. The author focuses on fossil fuels and also on the renewable energy sources. The amount of produced waste to the unit of produced energy, built up area, safety and economic indicators and other parameters are followed for each source of energy.
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New trends of disposal of radioactive waste
Vohralík, Lukáš ; Trtílek, Radek (referee) ; Matal, Oldřich (advisor)
The main point of my diploma thesis is accession the questions of disposal of radioactice waste and related proceeding with it. The thesis is engaged in estimation of the current disposal site in the Czech republic and analysis of the particular technological ways of the procces with radioactice waste.The thesis is engaged in real possibilities of maximum minimization radioactive waste in the Czech republic in the context of raising quantity radioactive waste. It is taken up new trends in disposal of radioactice waste and technology of the modification of radioactice waste before storing.
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Heat transfer in the storage cask and its impact on the environment
Marcell, Jan ; Slovák, Jiří (referee) ; Matal, Oldřich (advisor)
The main object of this diploma thesis is solving problems concerning heat transfer in disposal cannister for spent nuclear fuel. In forepart possibilities of conceptual solving according of disposal cannister to particular states are reviwed. On the basis of this a variant of possible protect of a nuclear fuel repository in the Czech republic has been chosen for calculationof a simplified model. Second part is computational solving that was divided into two parts. The first deals with calculation of heat transfer in disposal canister and is done by an analytical method. In the second part is calculation is done by numerical model. In this way region in near surroundings of this model of disposal cannister is analysed. Last part those diploma thesis deals with design of the storage of spacing among disposal canisters as well as optimum placing in underground part of nuclear fuel repository.
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