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Emergencies in nuclear power plants
Šupík, Ondřej ; Fiala, Miloš (advisor) ; Vilášek, Josef (referee)
Title: Emergencies in nuclear power plants Objectives: The aim of this work is to summarize information about emergency plans of nuclear power plants Temelín, Dukovany and the accident at the Chernobyl nuclear power plant. Methods: Descriptive-analytical methods are used as methods in this work. Study sources and their subsequent research were used to develop this work. Results: The result is a summary of information on the emergency plans of the Temelín and Dukovany nuclear power plants and on the accident was the largest nuclear power plant accident in history. The current nuclear power plants in the Czech Republic place great emphasis on the prevention of nuclear accidents and on the overall safety of operation. Keywords: analysis, event, power station, reactor, measure
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Separation of pollutants on photoreactors
Kurťák, Marek ; Šolcová, Olga (referee) ; Svěrák, Tomáš (advisor)
The diploma thesis deals with photocatalytic degradation of organic polutants on water- suspended UV activated anatase particles. The measurements are executed on a pilot plant UV photoreactor and the aim the thesis is to figure out the time course of azo dyes degradation under different photoreactor settings and subsequently infer the effectivity of the photoreactor under different settings. The degree of the aze dyes degradation is evaluated via UV-VIS spectrometry.
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Evaluation of introduction protection measures - evacuation at crash of nuclear power station Fukushima
SLÁMA, Filip
The aim of this bachelor thesis is to evaluate the protective measures, notably the evacuation of the population, its development and progress. To achieve the goal of bachelor's work was determined by the research question: Was the safeguard measures and the subsequent procedure for the evacuation of persons from the evacuation zones sufficient? The theoretical part is focused on the particular issue of nuclear power plants, radiation protection and evacuation. The situation described here, which took place directly on the Fukushima daiichi nuclear power plant Daiichi, from the strike of the earthquake and tsunami, after the gradation events in the individual reactors. The research part is about the development of the evacuation in the evacuation zones and the nuclear power plant. Protective measures are described here, and even the consequences and the situation after the crash to the present. The methodology of this work was the gathering of available information from official foreign sources, legislative documents, but also of the publications of the experts. Processing of the available information and the evaluation of the consequences of the evacuation has brought unpleasant findings. The loss of life, which can make a person look a certain way to reflect over the selection of persons suitable to evacuate. In this work were identified and discussed technical shortcomings of the power plant, the information misconduct in communication of the population and in the last row and misconduct of the human factor. The thesis can be used in the general issue of nuclear power plants and evacuation for study purposes or as an information source in the education, energy or public administration.
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Analysis of selected chemical parameters of Temelín Nuclear Power Plant primary circuit coolant
ŘEHÁČEK, Martin
The aim of the thesis was to define the meaning of radiochemical processes which take place in coolant of the primary circuit of the Nuclear Power Plant; and to describe the way of measurement of chemical parameters. The second aim was to define the significance of dissolved hydrogen to compensate for corrosion-threatening corrosion-safe operation of plant and to describe the method of generating hydrogen by ammonia. The third aim was to investigate the time courses of ammonia and hydrogen concentrations within the two production units. The last aim was to investigate unilateral dependence between ammonia and hydrogen concentrations. The first two aims were met by using system analysis of coolant chemical parameters, methods of measuring them, and ongoing radiochemical processes in the coolant. Ammonia and hydrogen were selected for deeper investigation, because of the results of the analysis. H1, H2 and H3 hypotheses have been formulated to meet the other two aims. The H1 hypothesis was used to verify the empirical distribution of ammonia and hydrogen concentration measurements by non-parametric normality testing. Hypothesis H2 investigated the time dependence of ammonia and hydrogen concentrations by regression analysis. In case of verification of H3 hypothesis the method of regression and correlation dependency was used. The verifying of hypothesis has shown that the empirical distribution of the measurement of hydrogen and ammonia concentrations is more closely related to the theoretical normal distribution. Furthermore, it was verified that the linear regression function of the time dependence of ammonia and hydrogen concentration measurements is close to the parallel to the timeline during the fuel campaign. Linear regression and correlation analysis confirmed that the correlation between hydrogen and ammonia concentrations is similar on both blocks and close to strong positive correlation. Verification of required regressive and correlative bending between ammonia and generated hydrogen can be understood as a practical contribution.
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Prototyp detektoru reaktorových antineutrin
Fajt, Lukáš ; Štekl, Ivan (advisor) ; Dragoun, Otokar (referee)
Title: Prototype of detector for detection of reactor's antineutrinos Author: Lukáš Fajt Department: Institute of Particle and Nuclear Physics Supervisor: Doc. Ing. Ivan Štekl, CSc., IEAP, CTU in Prague Abstract: This master thesis is related to the development of the complex detector of reac- tor's antineutrinos, so called S3 , which is based on the polystyrene scintillation detectors. The detector S3 (dimensions 40 x 40 x 40 cm3 ) will be located in the close vicinity of a nuclear reactor (5-12 m) and its purpose will be to measure reactor's power, isotopic composition of the nuclear fuel and moreover verification of the sterile neutrino hypothesis by detecting reactor's antineutrinos via the Inverse Beta Decay (IBD) interaction. Within the thesis, the first prototype of the antineutrino detector was constructed. It is composed of 18 scintillation plates (40 x 20 x 1 cm3 ) and corresponding electronics. With this prototype the first test with cosmic muons were performed. Within the thesis, the energy reso- lution of the scintillation plates was significantly improved by the optimization of their chemical composition and selection of the optimal refractive material. The proper energy resolution is very important for the detector functionality. In addition, a new methods for the production of coating layer...
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Accelerator Driven Nuclear Power Plants
Jarchovský, Petr ; Krása,, Antonín (referee) ; Katovský, Karel (advisor)
This bachelor’s thesis deals with utilization of spent nuclear fuel in nuclear power plants of new generation – accelerator driven nuclear power plants and of conversion of this fuel into electrical energy. In the introduction are listed basic physical and theoretical knowledge of nuclear reactors along with their basic division and global distribution. As another point accelerator driven systems are described with their brief development and the basic concept and usage on both the nuclear power plants and transmutation technologies. Some global projects are mentioned here dealing with this system and conduct research. More into detail is point about European projects MYRRHA and ESS, because there are important research facilities worldwide. The next are projects with liquid target as a very promising medium. The last part deals with the calculation of basic parameters of ADS in the MCNPX and its applying.
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Graphical processing of VVER 1000 simulation results
Kiš Bandi, Peter ; Novotný, Filip (referee) ; Vojáčková, Jitka (advisor)
This bachelor thesis describes core design of nuclear reactor VVER 1000 and deals with processing of results calculated by neutronics code PARCS in SNAP application suite. Nowadays, while designing or modifying nuclear reactor, it is very important to verify behavior of newly designed or modified parts in anticipation. For this purpose there are various computing programmes designed especially for these computations. However, to work with them is necessary to be familiar with the construction of the reactor core, because it is important to understand the results of the calculations. These can be shown either in form of text files or or processed into form of graphs and animations using various applications, in this case in SNAP application suite.
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Materials for IV. generation power plants
Hovorka, Martin ; Svoboda, Pavel (referee) ; Šnajdárek, Ladislav (advisor)
The aim of this thesis is to describe material needs of chosen Generation IV nuclear reactors – VHTR, SCWR, and MSR with the emphasis on the VHTR. It describes the main principle and a constructional arrangement of VHTR components with its material demands. SCWR and MSR reactors are described in terms of its material requirements. The middle part of this thesis is dedicated to the available material candidate analysis. Main material properties are discussed and at the end of this part the suitability of chosen materials for a flange joint in VHTR heat exchanger is assessed. The last chapter (the practical part) is focused on an experimental proposal of changeability of older materials by the new ones using the electron beam welding method.
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Inspection authorities of nuclear safety in the world and their purpose
Dvořák, Aleš ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This thesis deals with issues of nuclear safety. The first section provides an overview of international organizations and associations, which control via their activities all regulations concerning nuclear safety, the technical state of equipments and systems in nuclear power plants. The second part deals with technical description of important equipment and systems of the nuclear powerplants at chosen nuclear reactors of II. and III. generation. The last part explains the conception of nuclear safety deeply. The reader can gain a deep overview of the different levels of protection and attention is also paid to the methods that contribute to the evaluation of nuclear safety.
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Use of combination of bacteria and algae for wastewater treatment
Hlavsová, Barbora ; Stříteský, Lubomír (referee) ; Hlavínek, Petr (advisor)
The aim of this bachelor's thesis is to introduce the reader to the ever improving methods of biological wastewater treatment with the use of bacteria, algae and combination of both. Further it elaborates on the promising ways of utilizing biomass gained from these treatments in various sectors, such as energetics, chemistry, pharmacy and agriculture. The second part of the thesis offers a techno-economic study of wastewater treatment using combination of bacteria and algae in a specifically assigned area.
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