National Repository of Grey Literature 16 records found  1 - 10next  jump to record: Search took 0.01 seconds. 
Reseach of Molten Salt Cooled Nuclear Reactor Behavior
Kostečka, Jan ; Števanka, Kamil (referee) ; Katovský, Karel (advisor)
The master ‘s thesis deals with the studying behavior of nuclear reactors cooled by liquid salts and with application of liquid salts for IV. Generation of nuclear reactors. For the use of liquid salts, it’s necessary to change the concept of the structure of nuclear reactors. There are new ways to use new fuel in a liquid state. Each salt compound or a set thereof is original in its nature. Therefore, it is necessary to consider a suitable compound for the purposes employed. These points are discussed in the theoretical part. The thesis examines particularly chloride salts, with which there is not much experience. The practical part monitors and verifies the nuclear properties of chloride salts, in our case it is a solid-state chloride sodium chloride’s compound. In addition to the experimental measurement, the MCNP simulation program is used also.
Automatization of Analysis of Performance and Power Consumption
Rudolf, Tomáš ; Jaroš, Jiří (referee) ; Nikl, Vojtěch (advisor)
This thesis deals with increasing efficiency of supercomputers. Higher efficiency can be achieved by reducing frequency of processor if the algorithm does not slow down significantly. This thesis presents set of scripts designed to monitor consumption of processor along with scripts that visualize these measured values. It also allows easy control of processor frequency. The created solution gives user a capability to measure given algorithm efficiency and optimize computing power of specific computer exactly for the algorithm. Due to this work the user will be informed about whether it is advantageous to run his algorithm on one or other frequency of the processor.
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.
Current state of the construction of MSR reactors
Kotrnetzová, Daniela ; Svoboda, Pavel (referee) ; Šnajdárek, Ladislav (advisor)
This thesis describes Generation IV reactors with a detailed view on the molten salt reactors. There are described all types of these reactors individually and their current research. There is analyse of AHTR reactor and his possible configuration. At the end of this bachelor thesis is a processing of a heat loss from a pipe.
Transmutation of spent nuclear fuel with using accelerator driven systems
Máca, Pavel ; Král, Dušan (referee) ; Zeman, Miroslav (advisor)
This bachelor thesis deals with the analysis of neutron spectra in the reactors with liquid salts. The teoretical part contains a brief description of the nuclear fuel cycles. In the theoretical are further described the reactors of IV. generations. Here are the reactors on the basis of liquid salts described in detail. The practical part of the bachelor thesis is focused on the analysis of neutron spectra in set-ups performer from solid salt. Concretly, the salts NaCl and KCl were analysed by means of the computational codes TALYS and MCNP.
Methods for properties analysis of transmission lines
Žůrek, Dalibor ; Kočiš, Luboš (referee) ; Hadinec, Michal (advisor)
This work focuses on a search of available literature on the theory of transmission lines and verify the possibility of simulation processes on these lines using a suitable simulation program. Initially, for the introduction to the parameters and the phenomenon that characterize the line and are important for understanding the issue. These parameters are then measured and compared with traces from the simulation in program PSpice. In another part of the work, the reader is familiar with the basics of reflectometry and fault detection capabilities on transmission lines with the basic reflectometry methods TDR and FDR, as well as with other methods of OTDR, MSR, and PD-FDR. For the TDR, FDR and MSR methods were made experimental measurements with a view to determining the position of the various types of faults on the tested leadership.
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.
Transmutation of spent nuclear fuel with using accelerator driven systems
Máca, Pavel ; Král, Dušan (referee) ; Zeman, Miroslav (advisor)
This bachelor thesis deals with the analysis of neutron spectra in the reactors with liquid salts. The teoretical part contains a brief description of the nuclear fuel cycles. In the theoretical are further described the reactors of IV. generations. Here are the reactors on the basis of liquid salts described in detail. The practical part of the bachelor thesis is focused on the analysis of neutron spectra in set-ups performer from solid salt. Concretly, the salts NaCl and KCl were analysed by means of the computational codes TALYS and MCNP.
Automatization of Analysis of Performance and Power Consumption
Rudolf, Tomáš ; Jaroš, Jiří (referee) ; Nikl, Vojtěch (advisor)
This thesis deals with increasing efficiency of supercomputers. Higher efficiency can be achieved by reducing frequency of processor if the algorithm does not slow down significantly. This thesis presents set of scripts designed to monitor consumption of processor along with scripts that visualize these measured values. It also allows easy control of processor frequency. The created solution gives user a capability to measure given algorithm efficiency and optimize computing power of specific computer exactly for the algorithm. Due to this work the user will be informed about whether it is advantageous to run his algorithm on one or other frequency of the processor.
Reseach of Molten Salt Cooled Nuclear Reactor Behavior
Kostečka, Jan ; Števanka, Kamil (referee) ; Katovský, Karel (advisor)
The master ‘s thesis deals with the studying behavior of nuclear reactors cooled by liquid salts and with application of liquid salts for IV. Generation of nuclear reactors. For the use of liquid salts, it’s necessary to change the concept of the structure of nuclear reactors. There are new ways to use new fuel in a liquid state. Each salt compound or a set thereof is original in its nature. Therefore, it is necessary to consider a suitable compound for the purposes employed. These points are discussed in the theoretical part. The thesis examines particularly chloride salts, with which there is not much experience. The practical part monitors and verifies the nuclear properties of chloride salts, in our case it is a solid-state chloride sodium chloride’s compound. In addition to the experimental measurement, the MCNP simulation program is used also.

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