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The AmBe Laboratory Neutron Source Field Determination Using Experimental Stend
Jelínek, Martin ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
This master’s thesis provides a comprehensive overview of the conventional neutron sources from the perspective of reactions which lead to the production of neutrons, advantages, disadvantages, properties and their possible utilization. In the relation to the assembly of the laboratory neutron source and the unique experimental stand “Candle” basic methods of the neutron field analysis are outlined and two of them, the neutron activation analysis and the calculation using the MCNP software code are discussed in depth to apply and compare these methods. The experimental part deals with the realization of neutron activation analysis from its design itself, through gamma spectrometry to the cadmium ratio calculation. In compliance with the measurements, a calculation with MCNP code was run and both methods were evaluated and compared. The computation is complemented with the analysis of radiation situation on the borders of the supervised area, which is compared to the legal limit.
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Research and Development of Innovative Uranium Nuclear Fuel Matrices
Hrbáček, Tomáš ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
The bachelor thesis is focused on the issue of nuclear fuel used for nuclear reactors. It is dedicated to research of current trends in nuclear pellets. The qualitative parameters of nuclear fuels are described here, predominanly thermal conductivity and density of nuclear fuel. A special chaper of this thesis is devoted to the simulation and fuel additives during burnout. The final part of the bachelor thesis is dedicated to a specific design of material for a test research pellet.
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Limits and a World-Wide Status of New Nuclear Installations
Novák, Martin ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
This bachelor´s thesis deals with new nuclear installations from the beginning of nuclear era to the present installations. In the introduction of this thesis are mentioned historical events that led to the current nuclear power engineering. Furthermore, there is summarized the present world-wide state of nuclear energy and its share of the total electrical production. The introduction also contains the basic division of nuclear power plants into generations. Current and past construction of nuclear power plants is divided to the generations with focusing on development and construction of individual nuclear power reactor types. This thesis also characterizes the first nuclear era with evaluation of factors which had influence on development and construction of nuclear power plants in different countries. In next section is a world-wide status of new nuclear installations in comparison with past nuclear installations. The following section contains comparison of age of permanently shutdown reactors and operational reactors with respect to their future replacement. The thesis figures out the possibilities of increasing nuclear power capacity and life extension of nuclear power plants in operation. Furthermore, there is summarization of all projects that are currently in process of construction. This thesis is also focused on analysis of the construction delays of two European nuclear power plants Olkuluoto 3 in Finland and Flamanville 3 in France. Developments in these individual projects are sorted chronologically to the present state with pointing to the cause of delays. The detailed analysis contains the characterization of the main projects participants and their parts in the projects. In the final part of this thesis the author presents a description of construction some other nuclear power plants projects in the world.
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Ionizing Radiation, Residual Heat Generation, and Inventory of Spent Nuclear Fuel
Hájková, Barbora ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
This bachelor's thesis deals with ionizing radiation, residual heat generation, and inventory of spent nuclear fuel. It introduces types of ionizing radiation and half-life of isotopes, which are contained in the nuclear fuel. Furthermore, using code UwB1, a simulation of the burning of nuclear fuel used at the Dukovany Nuclear Power Plant from the introduction of fuel into the reactor to its storage in deep repositories in 2065, is carried out.
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New Trends in Ionizing Radiation Shielding Research and Development
Vláčil, Martin ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
This thesis deals with the problem of shielding ionizing radiation which is a beam that has enough energy to ionize an atom or a molecule of an irradiated substance. This radiation can occur in nuclear facilities such as a nuclear power plant, a particle accelerator, or in X-rays in healthcare. Until now, standard shielding materials, most often lead or concrete, have been used to protect against ionizing radiation. New trends are therefore trying to replace these materials with lighter, more effective and harmless materials. The practical part is focused on measure the data to obtain the basic properties of shielding materials, such as the attenuation factor and the buildup factor. A measuring platform is described here, which can be used to measure the data needed to calculate the attenuation factor and the buildup factor. The measurement results are compared with tabular values to determine the accuracy of the measurements. Furthermore, the results of measurements of five concrete materials from the company MICo, spol. s r.o. To obtain theoretical values, the simulation program MCNP6 was used, in which it is possible to create a model of the measuring platform, which was used in practical measurements. Next the shielding material, source and detector are defined. The result lead again to the data needed to determine the attenuation factor. The results of measurement and simulation data in MCNP6 are evaluated and graphically processed into such a form that it is possible to compare the properties of shielding materials with each other.
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Simulation and measurement of neutron field by Bonner spheres
Arbeit, Vít ; Šťastný, Ondřej (referee) ; Mičian, Peter (advisor)
The objective of this master’s thesis is introduction, explanation and practical demonstration of simulations conducted in program PHITS. The first part analyses neutrons and related issues regarding their detection as well as neutron sources. Next part is focused on program PHITS, both on it’s basic and advanced functions. Practical part of this thesis deals with the simulations of Bonner spheres and their responses to neutrons of different energies under different conditions. It also compares the results obtained through simulations with measured data.
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Study of alternative ending of nuclear fuel cycle in the Czech Republic
Michalica, Jaroslav ; Radil, Lukáš (referee) ; Šťastný, Ondřej (advisor)
This bachelor thesis deals with the alternative end of the nuclear fuel cycle in the Czech Republic. At the beginning of the work, the nuclear fuel cycle is explained, then the radioactive waste, how it is produced, and how we divide it. This is followed by a chapter that deals with the removal of the used nuclear fuel, from its extraction from the reactor through its temporary storage until its final disposal in an underground waste repository. The work then explains the alternative of direct disposal of used nuclear fuel, namely reprocessing of used nuclear fuel. It explains the existing methods for the reprocessing of used nuclear fuel which are currently being used, and where the used nuclear fuel reprocessing plants are located. The conclusion of the thesis deals with the economic comparison of direct final disposal of used nuclear fuel with reprocessing and final disposal of radioactive waste.
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The temperature field analysis of the subcritical accelerator-driven reactors
Majer, Šimon ; Šťastný, Ondřej (referee) ; Svoboda, Josef (advisor)
The aim of the bachelor thesis is to discuss the problems of accelerator driven system, to describe the possibilities of temperature measurement, to create model of the spallation target QUINTA target in the program Inventor and to perform the simulation by using the Ansys software. The theoretical part is focused on nuclear energy and its potential for the future and continues smoothly to the issue of accelerator driven system (ADS), where it discusses the possibilities of using mentioned system. The thesis is processed from the point of view of electrical energy, focusing on generation issues and the possibility of heat monitoring. The possibilities of temperature measurement are discussed here for calculation and simulation of heat transfer. The practical part of the bachelor’s thesis is processed with the help of the Joint Institute for Nuclear Research in Dubna, where the ADS research is in process. The input data and the size of the geometry were provided by the JINR research team and were used to simulate heat transfer by using the Ansys program. The results of the simulation are processed graphically in the last chapter of the bachelor thesis.
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Determination of nuclear reactions' microscopic cross-sections using an accelerator-driven neutron source
Filová, Vendula ; Šťastný, Ondřej (referee) ; Král, Dušan (advisor)
Tato práce se věnuje určení mikroskopických účinných průřezů interakcí neutronů s indiem. Teoretická část shrnuje neutronové zdroje používané ve vědě i průmyslu, popisuje princip jejich fungování a představuje příklady jejich aplikací. Praktická část obsahuje postup vyhodnocování velikostí účinných průřezů včetně jednotlivých provedených korekcí. Byly vyhodnocována data celkem ze tří experimentů, při kterých byly produkovány neutrony interakcí protonů s tenkým lithiovým terčem. Kvazi monoenergetickým neutronům byly vystaveny sendviče folií včetně foile z india, produkty interakcí byly měřeny pomocí gamma spektrometrie. Výsledné mikroskopické účinné průřezy jsou porovnány s daty z knihoven evaluovaných dat a z knihovny EXFOR.
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Radiation detection, shielding and identification in public safety.
Kumičák, Ivan ; Šťastný, Ondřej (referee) ; Varmuža, Jan (advisor)
A problem of ionizing radiation is considered in this thesis. The work consists of few chapters, where types of ionizing radiation and its interaction with material environment, also separate measures, which characterize both a source of ionizing radiation and influence of ionizing radiation on a life form are describes. Kinds of detectors of ionizing radiation and principles of their running are taken up as well.
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