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Fast molten salt reactor simulation
Dzurňák, Martin ; doc. Ing. Pavel Zácha, Ph.D., ÚE FS ČVUT v Praze (referee) ; Katovský, Karel (advisor)
This thesis deals with the sensitivity analysis of a molten salt fast reactor. The computational sensitivity analysis is carried out in the MCNP program. After an introduction to molten salt reactors and an overview of molten salt fast reactor projects, the Stable Salt Reactor - Wasteburner project is selected for sensitivity analysis. The development of the reactor model in MCNP is described. Sensitivity analysis is performed on the influence of the nuclear data library, reactor temperature and the influence of the fuel salt composition.
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Nuclear Fuel and its Behavior during Burn-up
Matocha, Vítězslav ; Foral, Štěpán (referee) ; Katovský, Karel (advisor)
The point of this bachelor’s thesis is to characterize different types of nuclear fuels and their behaviour during the process of burning-up. Futher, basic types of nuclear reactors are mentioned, as well as their history and different kinds of nuclear fuels used in these reactors. Then there are pieces of information about fuel cycles and fuel burning-up. Furthermore, the thesis concentrates on the changes, which happen in the nuclear fuel during the process of burning-up, such as swelling and cracking. In its other parts, this bachelor’s thesis deals with fission products, mainly gas fission products are mentioned here. At the end of this thesis, a simple model of nuclear fuel burning-up is created. This model follows concentration of izotopes of uranium and plutonium during fuel burning-up.
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Simulation of nuclear fuel burn-up during whole fuel cycle
Smola, Luděk ; ČEZ,, Ondřej Zlámal, (referee) ; Katovský, Karel (advisor)
The main goal of this Bachelor’s thesis is to create a long-term kinetics model of a nuclear reactor – model, which simulates changes in nuclear fuel inside the reactor core during reactor operation. As the term long-term suggests, primarily the changes in whole five-year fuel cycle horizon are studied, which stands for changes in concentration of elements contained within fresh fuel as well as origination of new ones (with special focus on higher actinides and plutonium). This mathematical model is created using the MAPLE 14 software. Outputs from the model are displayed graphically and thoroughly analysed, so that comprehensive conclusions of problems can be made. Furthermore, the thesis contains theoretical and informational background that is necessary for understanding all the aspects of the model – historical development of nuclear reactors, their basic types, nuclear fuel description focusing on fuel for pressurized light-water reactors VVER (for which the model is primarily designed), MOX fuel and possibilities of its utilization, and last but not least – selected topics from nuclear physics.
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Sodium cooled fast reactors
Daňhel, Aleš ; Katovský, Karel (referee) ; Foral, Štěpán (advisor)
This bachelor’s thesis deals with the sodium-cooled fast reactors. It comprehensively describes the problem of sodium-cooled fast reactors. Attention was paid to the basic specifications and parameters of these reactors. There was briefly described nuclear reactions which are under way in core of sodium-cooled fast reactors but also chemical reactions which are linked to function of liquid sodium as a coolant and heat transfer substance. Attention was also paid to the differences in the reactor core configuration and to the machine device specific for sodium-cooled fast reactors. Further on this bachelor’s thesis puts on the overview of sodium-cooled fast reactors that have worked, are still working or are under construction in each country all over the world. There was briefly described generation IV nuclear reactors, particularly its history and reasons that originate generation IV. Under generation IV was also described nuclear reactor SFR and highlighted differences compared to existing sodium-cooled fast reactors. In the practical part of this bachelor’s thesis is easily made a calculation of the heat transfer from the fuel rod to the cooling sodium and there is also mentioned course of the heat transfer coefficient along the fuel rod. This calculation was made by computing program MATLAB.
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The history and the present of nuclear weapons in the world and in The Czech Republic
TEJC, Michal
This bachelor thesis deals with the history and the present of nuclear weapons in the world and in the Czech Republic, from the first research in the area of the discovery of physical particles to the development and testing of nuclear weapons of individual states, the adoption of international treaties and agreements that reduce dangerous nuclear weapon abuses in the world. In the theoretical part, it contains historical references to discovering new elements, their research and practical use in nuclear weapons. The thesis also describes the clear history of the individual research programs of states that have now declared themselves or are expected to hold nuclear weapons or are currently developing nuclear weapons. The thesis continues with the analysis of international treaties and agreements on gradual banning of nuclear weapons testing, which resulted in the adoption of the Non-proliferation Treaty. The aim of this thesis was to: Analyze and compare the historical development and present of nuclear weapons in the world and in the Czech Republic. In order to meet this goal, it was necessary to address the persons who are oriented in the given issue and to use the processed questionnaires to characterize individual views of the respondents on the issue of nuclear weapons use or abuse, documenting accepted international treaties and possibilities of real nuclear weapons abuse by states that did not join international commitments. After responding people and analyzing their responses to nuclear weapons, materials that could be used to manufacture them, and controlling their non-proliferation, it was documented that all respondents agreed that international agreements led to lower international tensions and partial suspension of nuclear tests. In most countries, nuclear programs have either ended, or their nuclear program has been completely resolved beyond the guarantee system. By adopting current legal acts, the possibilities to illegally manufacture nuclear weapons have decreased. This does not apply to countries that support international terrorism and nuclear deterrence.
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Variations of actinide magnetism in uranium-base hydrides and other selected systems
Adamska, Anna Maria ; Havela, Ladislav (advisor) ; Arnold, Zdeněk (referee) ; Figiel, Henryk (referee)
Title: Variations of actinide magnetism in uranium-base hydrides and other selected systems. Author: Anna Maria Adamska Department / Institute: Department of Condensed Matter Physics Supervisor of the doctoral thesis: Doc. RNDr. Ladislav Havela, CSc., the Department of Condensed Matter Physics Faculty of Mathematics and Physics Charles University, Prague, Czech Republic and Assoc. Prof. Dr. hab. Nhu-Tarnawska Hoa Kim Ngan, Institute of Physics, Pedagogical University, Kraków, Poland. Abstract: Actinide magnetism was studied in three different types of systems. Variations of magnetic properties of UTGe hydrides as a function of hydrogen concentration prove that doping of U intermetallics by interstitial hydrogen leads to stronger magnetic properties, primarily caused by an increase of the inter-uranium separation. Sputter-deposited UFe2+x films, which are derived from the UFe2 Laves phase but have an amorphous structure, exhibit an increase of the Curie temperarture (to more than 400 K) with the Fe excess, which could not be achieved in the bulk. This is understood as a result of the prominent role of the 3d magnetism of Fe. Notoriously weakly magnetic plutonium was studied in the form of the alloy in the ζ-phase, which exists between 35 and 70 % U in Pu. Its susceptibility increases in a comparison to pure...
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Simulation of nuclear fuel burn-up during whole fuel cycle
Smola, Luděk ; ČEZ,, Ondřej Zlámal, (referee) ; Katovský, Karel (advisor)
The main goal of this Bachelor’s thesis is to create a long-term kinetics model of a nuclear reactor – model, which simulates changes in nuclear fuel inside the reactor core during reactor operation. As the term long-term suggests, primarily the changes in whole five-year fuel cycle horizon are studied, which stands for changes in concentration of elements contained within fresh fuel as well as origination of new ones (with special focus on higher actinides and plutonium). This mathematical model is created using the MAPLE 14 software. Outputs from the model are displayed graphically and thoroughly analysed, so that comprehensive conclusions of problems can be made. Furthermore, the thesis contains theoretical and informational background that is necessary for understanding all the aspects of the model – historical development of nuclear reactors, their basic types, nuclear fuel description focusing on fuel for pressurized light-water reactors VVER (for which the model is primarily designed), MOX fuel and possibilities of its utilization, and last but not least – selected topics from nuclear physics.
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Sodium cooled fast reactors
Daňhel, Aleš ; Katovský, Karel (referee) ; Foral, Štěpán (advisor)
This bachelor’s thesis deals with the sodium-cooled fast reactors. It comprehensively describes the problem of sodium-cooled fast reactors. Attention was paid to the basic specifications and parameters of these reactors. There was briefly described nuclear reactions which are under way in core of sodium-cooled fast reactors but also chemical reactions which are linked to function of liquid sodium as a coolant and heat transfer substance. Attention was also paid to the differences in the reactor core configuration and to the machine device specific for sodium-cooled fast reactors. Further on this bachelor’s thesis puts on the overview of sodium-cooled fast reactors that have worked, are still working or are under construction in each country all over the world. There was briefly described generation IV nuclear reactors, particularly its history and reasons that originate generation IV. Under generation IV was also described nuclear reactor SFR and highlighted differences compared to existing sodium-cooled fast reactors. In the practical part of this bachelor’s thesis is easily made a calculation of the heat transfer from the fuel rod to the cooling sodium and there is also mentioned course of the heat transfer coefficient along the fuel rod. This calculation was made by computing program MATLAB.
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