|
|
The 4th generation of nuclear reactors
Mlčúch, Adam ; Šnajdárek, Ladislav (referee) ; Nerud, Pavel (advisor)
This thesis reviews the particular generations of nuclear reactors. The biggest part of the thesis focuses on the projects of the fourth generation reactors. The individual projects come out from the analysis of the international forum GIF. The last part is devoted to the detailed description of VHTR system and demonstration plant concept with reactor Antares.
|
|
|
The 4th generation of nuclear reactors
Katzer, Milan ; Škvařil, Jan (referee) ; Nerud, Pavel (advisor)
My thesis reviews the particular generations of nuclear reactors. The greatest part of the thesis focuses on the groundbreaking projects of the IV.generation reactors, which should be put into operation in 2030 or later. The individual projects come out from the analysis of the international forum GIF where six revolutionary nuclear reactors were chosen. The last chapter is devoted to the detailed description of one of the chosen reactors and its possible installation in the Czech Republic.
|
|
|
Project of nuclear power unit secure emergency power supply for design basis accident as well as for extension conditions
Žák, Tomáš ; Šťastný, Jiří (referee) ; Katovský, Karel (advisor)
The present Master´s thesis aims at designing an evolutionary scheme of secured power supply at nuclear power plants with VVER 440 reactors during design basis accidents as well as design extension conditions. In the first part of this thesis, concepts relating to the defence in depth of nuclear reactors, operating modes of the blocks as well as types and possibilities of electrical power supply and electric circuits of the block are defined. Although the present thesis deals with PWR 440 in general, special emphasis is put on the Czech NPP in Dukovany, where there are four PWR 440 reactors in operation, and on the possibilities for enhancing the defence in depth in this area. The second part of the thesis deals with the difference in station blackout definitions before and after Fukushima; not only the differences in situation evaluation are dealt with, but a solution is also proposed to make the system of secured power supply system during design basis accidents as well as design extension conditions more robust. This option has been selected out of a number of possibilities based on the evaluation of reliability, availability and cost-effectiveness of the proposal.
|
|
|
Review of world nuclear reactors
Blažková, Eva ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This bachelor work is focused on creating an overview of nuclear reactor types, their categorization and engineering approach to particular designs. Furthermore, it also lists countries having nuclear reactors in possession and their standpoint towards nuclear energy in general. A brief summary of the third and fourth generation and their future energy potential is included as well. This work primarily reflects present-day status.
|
|
|
Nuclear power plants and their safety
Novotný, Petr ; Köbölová, Klaudia (referee) ; Milčák, Pavel (advisor)
The bachelor thesis deals with the current state of nuclear energetics. It describes the development of nuclear power plants to date and specifically describes the most commonly used types of nuclear reactors. Most of the reactors currently in operation are second generation reactors. However, a number of third-generation reactors with improved technological and safety parameters are already under construction. Improved safety lies in the improvement of active safety systems, but also in the increased use of passive safety systems. The paper concludes with a comparison of specific solutions from the most important nuclear reactor manufacturers in the world.
|
|
|
Severe accidents of third generation pressurized water reactors
Nečas, Karel ; Foral, Štěpán (referee) ; Černý, Tomáš (advisor)
The bachelor thesis focuses on the development of global nuclear energy. It clearly describes the development and division of nuclear facilities used for electricity production. The theoretical part of the thesis describes the division of nuclear facilities according to the development generations, the types are discussed in terms of technology and principle of operation. The operating conditions of nuclear reactors are described in detail, with emphasis on emergency conditions. The next part of the thesis focuses on the LOCA accident type for third generation pressurized water reactors. This thesis also includes an analysis of different approaches od the computation codes used for modelling various conditions of the nuclear power plants. The practical part of the bachelor thesis describes nuclear reactor APR1400. It provides its elementary parameters. The calculation code MELCOR was used for modelling this type of the nuclear reactor. The sensitivity analysis of the severe accident was performed using selected parameters. This analysis describes the influence of these parameters on the hydrogen production, the process of damaging of the active zone, and the reactor vessel melting time.
|
|
|
Example determination of departure from nucleate boiling ratio
Křeček, Tomáš ; Števanka, Kamil (referee) ; Foral, Štěpán (advisor)
This Master's thesis deals with the issue of departure from nucleate boiling in the APR1400 nuclear reactor. First, reactor design is described, particularly the reactor core and fuel assemblies. Then the thesis focuses on explaining the issue of boiling crisis in nuclear reactors. The main objective of the thesis is to create and validate a model of the reactor core of the APR1400 reactor using the subchannel program ALTHAMC12. The created model is validated by comparasion with a reference study, and finally, the thesis addresses a sample calculation of the departure from nucleate boiling ratio using data provided by TES s.r.o. company.
|
|
|
Emergency and current exposure situation in residential areas of Fukushima prefecture - aspects of communication of low dose risks
ŠÁROVÁ, Romana
The diploma thesis examines the post-accident and current exposure situations in residential areas of the Fukushima prefecture and discusses certain aspects on communication concerning the risks of low doses. The evaluation was based on research and collection of information and data from printed and electronic resources. The results show the sequence of steps carried out by the Fukushima prefecture and IAEA and the degree to which they were successful. The aim of the diploma thesis is to offer a clear comparison of the monitoring of the post-accident situation in specific areas of the Fukushima prefecture and the situation achieved after a comprehensive decontamination and remediation of the environment. We compared the measured values of the current radiation situation at the Fukushima prefecture with values in the Czech Republic, available thanks to the MONRAS application. The thesis also examines how the authorities communicated with the people of Fukushima before the evacuation and in the period after the evacuation when the habitable part was decontaminated and the government sought (and still seeks) to return people to these areas. I also explored the approach to the optimisation of radiation protection in Fukushima, how this principle can be interpreted in the Czech Republic and how to contribute to sufficient awareness of the population in terms of a general understanding of the limits and optimisation of radiation protection in case of a nuclear accident. For this purpose, an informational brochure was created using the Canva Pro online tool. This brochure represents the practical output of the diploma thesis. The decontamination efforts can be considered successful, given that the measured content of caesium in the environment has been radically lowered; one negative consequence was the creation of a large amount of radioactive waste. The air dose rate is comparable to general global background radiation. The residents therefore don't need to be afraid to return to their homes.
|
|
|
Safety problems of modern nuclear reactors
Kukla, Jaroslav ; Přibil, Rudolf (advisor) ; Matějíček, Luboš (referee)
Jaroslav Kukla Otázky bezpe nosti moderních jaderných reaktor Bakalá ská práce Abstract: This study is concerned with safety factors of nuclear reactors. It summarizes history of nuclear reactors development and analyses causes of some serious accidents, which occurred in the past. It describes physical characteristics of radioactive radiation and mentions a basic survey of quantities and units. Then it describes the influence of radioactive emission on man and other living organisms. It also defines some reactor components and focuses on general security principles, which are further developed. It shortly explains the methods of evaluation of safety factors of nuclear reactors and a role of nuclear supervision. It puts nuclear reactors into several generations and every type of reactor is described as for technical and safety aspects, respectively. It refers to contemporary trends in development of nuclear reactors and in development of their safety.
|
|
|
Environmental Impact Assessment of the Atomic Power Station Jaslovské Bohunice
Ušáková, Diana ; Matějíček, Luboš (advisor) ; Přibil, Rudolf (referee)
The impacts of nuclear power are now very important component of the impact assessment of the energy industry on the environment. The first nuclear power plant, which was built in the former Czechoslovakia is nuclear power plant called Jaslovské Bohunice, which is located in the western part of the Slovak Republic. Environmental load, but compared with thermal power plants is much lower, since the nuclear power plant produces smaller amounts of emissions and greenhouse gases such as thermal power plant. The concentration of radioactive substances in the ambient atmosphere and hydrosphere is much lower than permissible limits. Dispersion of harmful radioactive substances, however, implemented a broad area. Bohunice nuclear power plant is equipped with a special system for processing radioactive waste and the management of it, which is a major advantage in the use of these technologies. The survey population around Jaslovské Bohunice concerned people of various ages who were mostly university education. The public, which the operation of a nuclear power plant directly relates to the earlier welcomed the development of nuclear energy in Slovak as the forced outage. The questionnaire revealed that much of the population does not have the necessary data regarding the management of radioactive waste. The...
|
guest ::
