National Repository of Grey Literature 86 records found  1 - 10nextend  jump to record: Search took 0.01 seconds. 
Enrichment and reprocessing of nuclear fuel
Janoušek, Petr ; Elbl, Patrik (referee) ; Sitek, Tomáš (advisor)
Nuclear fuel is one form of electricity generation. This bachelor thesis deals with its modification and processing as this fuel has to undergo special processes to ensure its good usability. The aim of the thesis is to list and analyze the main processes involved in the production of nuclear fuel. The thesis is, in particular, focused on the enrichment of nuclear fuel, which is the process of enhancing its properties. The first and second chapter of the paper discusses basic issues of first nuclear energy and then nuclear fuel. The third chapter of the thesis explains in detail the enrichment of nuclear fuel and also describes different methods of enrichment. Another process taking place after nuclear fuel is used is it's reprocessing. This method of converting used fuel into fuel that can be reused is dealt with in the last chapter of the thesis.
Analytical methods applied for the evaluation of environmental contamination by uranium ore mining
Bílek, Jiří ; Holubová, Zuzana (referee) ; Čáslavský, Josef (advisor)
This thesis deals with the testing procedures used in monitoring of environmental contamination after uranium ore mining in the uranium mine in Dolní Rožínka. It deals with the determination of radioactive elements radium, uranium and radon. The methods used for the determination of radioactive elements in mine laboratory in Dolní Rožínka are described. The thesis also mentions other applicable methods for determination of uranium. The metods of determination of manganese, iron and other metallic elements are also summarized in brief.The values of concentrations of monitored analytes in selected locations are presented at the end of the thesis. These values, which were provided by laboratories in Dolní Rožínka, are valid for 2010.
Nuclear energetics in CR and in the world
Peroutka, Tomáš ; Bartošík, Tomáš (referee) ; Mastný, Petr (advisor)
This work is about a basic principles of nuclear reaction, creation of nuclear reaction and its development. Here is also described contemporary status and its level of progression. The first part is about a history of nuclear energy – its beginnings and further progress. Next the work deals with a nuclear power stations, nuclear reactors etc. The other part of this work is based on a nuclear waste. Then, I will write about a future of nuclear energy. The last point is creating the enegetic conception of our country.
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.
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.
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.
MONITORING OF URANIUM IN DRINKING WATER IN THE SOUTH MORAVIAN REGION AND ITS ANALYSIS.
Hanusková, Vendula ; Doležalová Weissmannová, Helena (referee) ; Ing.Dita Janečková, (advisor)
The determination of uranium in samples of the enviroment was considered for liquadeted chemical toxicity of uranium and it is impossible to leave out a potential occurrence in drinking water. The purpose of this diploma thesis was the monitoring of preselected public water supplies in the South Moravia and post action analysis of those samples. That was all on the basis of the requierement of the Regional Hygiene Station. For determination of trace concentrations of uranium in drinking waters the method ICP-MS (Inductively Coupled Plasma with Mass Spectrometry) was chosen. All of the results were then summarized and evaluated. At the end are proposed feasible solutions and precautions for public water supplies operators.
Determination of radionuclides in water and sediments
Bílek, Jiří ; Holubová, Zuzana (referee) ; Komendová, Renata (advisor)
This thesis has been prepared for DIAMO, Branch GEAM Dolní Rožínka. Literature research includes a description of the ionizing radiation, natural radionuclides, mining of uranium ore and mineral deposits; Běstvina and Licoměřice. The experimental part includes sampling, analysis and evaluation of the content of selected radionuclides in the two selected locations. The content of uranium and radium in sludge from mine water treatment plant is determined annually by an external laboratory, using of semiconductor gamma-spectrometric analysis (GSA). Determination of both radionuclides in waters in these areas is carried out in the Centre of testing laboratories (SZLAB) in Dolní Rožínka. Uranium and radium activity is below the detection limit. Sludges from Běstvina, according to the results of external laboratories, routinely show activity of both radionuclides. But activity in the waters from this locality is below the detection limit. The goal of this diploma thesis is to verify the radionuclide content in sludge from CDV Běstvina by another method. As a comparative method was chosen determination of uranium using the UV-VIS spectrophotometry with separation on silicagel. Location Licoměřice was chosen as a reference. Like a supplementary method for determining the concentration of uranium was chosen ICP-MS. For the determination of the radium was chosen radiochemical method scintillator ZnS (Ag).
Front end of the fuel cycle
Sedlák, Miroslav ; Katovský, Karel (referee) ; Foral, Štěpán (advisor)
Bachelor thesis will work of the front of the fuel cycle. Summarize and describe the current knowledge related to uranium, the phase transformation of unemployable chemical element for mankind significant energy source. Understanding the process of processing uranium to energy source is invaluable importance for the future of energy. The use of uranium as fuel only brings advantages inherent in the usability element for humanity, but also the disadvantege of environmental threats and the threat of negative censequences to the environment in case of accidents. A thorough knowledge of the various stages of the fuel cycle contributes to increasing the safety of use of this chemical element for mankind and increasing efficiency in the conversion of uranium ore, thereby creating still more favorable conditions for the development of nuclear energy.
Front and Back End of the Nuclear Fuel Cycle
Winterová, Radka ; Mastný, Petr (referee) ; Katovský, Karel (advisor)
In this bachelor thesis author deals with the topic of nuclear power fuel cycle and the particular differences that are typical for each nuclear reactor types. The author aims to describe in detail both - the front and especially the back end of the nuclear fuel cycle, fuel fabrication for light water nuclear reactors, fuel reprocessing and recycling, and consequently fuel production based on REPU and MOX. Thesis should also get familiar with global approaches to fuel cycle, especially the back end.

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