|
|
Nuclear Fuel in Operational Conditions
Konopová, Tamara ; Novotný, Filip (referee) ; Katovský, Karel (advisor)
This thesis deals with the issue of nuclear fuel. Firstly, the problem of nuclear fuel in the implementation for certain reactors is presented. Production of nuclear fuel is introduced, which includes the performance of companies engaged in the production of this fuel. Secondly, the phenomena in the fuel burnup are discussed. Lastly, the burnable absorbers are mentioned and the analysis of burnable absorbers is carried out.
|
|
|
Sensitivy analysis of the influence of manufacturing inaccuracies on the nuclear fuel reactivity
Sedlák, Martin ; Katovský, Karel (referee) ; Novotný, Filip (advisor)
This thesis deals with a sensitivity analysis of the influence of manufacturing inaccuracies on the reactivity of nuclear fuel. Sensitivity analysis has been done for fuel assembly TVSA-T, for nuclear reactors VVER-1000. Particularly, for fuel rod of type tvel - without burnable absorbers. Thirty three combinations of maximal and minimal of manufacturing parameters were simulated in SCALE environment. Changes of multiplication coefficient in dependence on burnup for 5 combinations have been also studied. It has been found that the most significant influence on the reactivity has the accuracy of enrichment and outer diameter of cladding. It has also been found that influence of manufacturing inaccuracies is not constant during burnup. The benefit of the thesis is determining the effects of individual inaccuracies on the reactivity and the fact that their influence is not constant during burnup.
|
|
|
Hodnocení spolupráce obcí v SO ORP Kuřim jako faktoru rozvoje venkova
Novotný, Filip
The main objective of this bachelor thesis is to provide a comprehensive assessment of inter-municipal cooperation in the administrative district of Kuřim municipality with extended powers through the project Municipalities for themselves. The thesis deals with the historical development of settlement structures and public administration in the Czech Republic. It describes various forms of inter-municipal cooperation and - in its research section - analyzes the interviews with local officials of the administrative district obtained on basis of a semi-standardized research. The research proved that the inter-municipal cooperation is rather informal, its potential in the area is not fully developed and the project did not bring about substantial changes in this respect. Thanks to considerable amount of information gathered, the thesis subsequently evaluates the effectiveness of the project in the administrative district and addresses the question of whether the set goals were successfully achieved.
|
|
|
Nuclear Fuel in Operational Conditions
Konopová, Tamara ; Novotný, Filip (referee) ; Katovský, Karel (advisor)
This thesis deals with the issue of nuclear fuel. Firstly, the problem of nuclear fuel in the implementation for pressurized water reactors is presented. Production of nuclear fuel is introduced, which includes the performance of companies engaged in the production of this fuel. Secondly, problems of nuclear fuel during operation, focusing on burnable absorbers and phenomena in the fuel burnup are discussed. Lastly, the calculation is carried out and gadolinium as a burnable absorber is compared with erbium as a burnable absorber.
|
|
|
Accidents of light water reactors
Bejček, Patrik ; Novotný, Filip (referee) ; Foral, Štěpán (advisor)
This thesis deals with the description of primary and secondary circuit of nuclear power plant with reactor VVER-400. Moreover, this thesis describes nuclear safety, its particular factors, and also international nuclear event scale. It is followed by a description of companies playing a significant role in the field of nuclear safety and a close attention is paid to SÚJB. In a section dedicated to nuclear safety, the focus is on events which can occur in nuclear power plant. In addition, the accident Large Break LOCA is described in detail. The practical part deals with the description and instructions to simulator PCTran developed by Micro-Simulation Technology. In the last part, there is an analysis of selected parameters which are simulated in simulator PCTran, parameters simulated in simulator RELAP5 5 and also the calculation of the temperature parameters of fuel TVSA-T and their simulation.
|
|
|
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.
|
|
|
Power and Temperature Distribution in Nuclear Fuel Assemblies of VVER-440 reactor at Dukovany NPP
Smola, Luděk ; Novotný, Filip (referee) ; Katovský, Karel (advisor)
This Master’s thesis focuses on calculation of power and temperature distribution in fuel assemblies of VVER-440 reactor at Dukovany Nuclear Power Plant. Theoretical section contains a brief description of VVER-440 technology, fuel and its development at Dukovany Nuclear Power Plant, basics of heat generation in nuclear reactors as well as an overview and categorization of computer codes, used for core calculations. Of these codes, the MOBY-DICK computer code is then described in depth, including its input and output files. The MOBY-DICK code is later on used for pinwise calculating power distribution of selected fuel cycles of defined units at Dukovany Nuclear Power Plant, with vizualization of output values for characteristic fuel assemblies. Results of this computation are then used for analysis, whether uneven power distribution in the core and heat generation gradient within fuel assemblies have any influence on measuring channel output temperatures, which is the pivotal part of this thesis.
|
|
|
Depletion calculation of VVER 1000 reactor fuel using KENO code
Janošek, Radek ; Katovský, Karel (referee) ; Novotný, Filip (advisor)
The introduction to operational nuclear reactors focusing on light-water pressurized reactor VVER 1000 is in the beginning of this Master´s thesis. This thesis covers basic technology of VVER 1000 reactor with focus on reactor core and nuclear fuel TVSA-T. A significant part of the thesis deal with basic concepts of nuclear safety and its methods. The main goal is to create a model of VVER 1000 reactor, which can be used in nuclear burn-up calculations using KENO code. Therefore a part of this thesis deals with explanation of statistical Monte Carlo method and the KENO code.
|
|
|
Description and Utilization of Small and Medium Sized Nuclear Reactors
Novotný, Filip ; Sklenka,, Ľubomír (referee) ; Katovský, Karel (advisor)
This Bachelor’s thesis examines the area of small- and medium-sized nuclear reactors and their roles in the early development of nuclear energy. The work covers current small- and medium-sized reactors in operation and considers future developments in this area. Included is an analysis of the possibilities for their use and applications in various areas of human activity. The work focuses on new projects of small- and medium-sized reactors, especially on projects considered for the near future. They are evaluated for nuclear weapons proliferation resistance, as well as their economic and technical advantages. Furthermore, an analysis was carried out of the possible uses of small reactors in propulsion of spaceships, and their use in various geographic areas. Knowledge acquired from this analysis applies to the situation in the Czech Republic. Both unrealized projects, and projects which may be realized in the future, have been described.
|
|
|
Computational analysis of pressurized water reactor core behaviour using PARCS code
Novotný, Filip ; Ing. Jan Frýbort, Ph.D., KJR FJFI ČVUT v Praze (referee) ; Katovský, Karel (advisor)
The Master Thesis performs search concerning advanced small and medium power light-water reactors’ designs, including different possibilities to gain a license for their development and operation. The work covers the principal theory about the area of neutronics calculations, principal equations and simplifications. There are several different methods for solution of neutronics calculations. The thesis gives an overview of two principal groups of codes – deterministic methods and Monte Carlo method. The survey shows computational codes examples based on mentioned methods. The computational code PARCS is chosen for further study, which contained description of the input and output file, process of the model creation and conditions for neutronics calculation the of selected reactor design. Based on these facts, the transient calculation has been prepared within the thesis. Thee analyses are described – reactor emergency shutdown, reactor shutdown with stuck group of control and emergency shutdown rods and reactor shutdown with faulty reaction of emergency shutdown rods.
|
guest ::
RSS feed.