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Analysis of the innovated nuclear fuel with FEMAXI code
Čásar, Ondřej ; Novotný, Filip (referee) ; Foral, Štěpán (advisor)
This bachelor thesis deals with modification of source code of program FEMAXI 6 and subsequent analysis of composite nuclear fuel based on SiC admixture. First part introduces the entire open fuel cycle, from the start of the mining to the final disposal of the nuclear waste. The following part describes physical processes in the fuel, especially the processes associated with the low thermal conductivity of classical uranium oxide ceramic pellets, contains the description of the temperature calculations in the pellet and the analysis of the thermal conductivity coefficient including the influences affecting its size. One part of the thesis is an analysis of selected composite fuels increasing the thermal conductivity and introduction of a computational program for FEMAXI 6 nuclear fuel analysis, including its structure, implementation of equations and description of the input file. In the practical part, one can find a description of performed program modifications, comparison with other computational programs and analysis of possible composite nuclear fuel for Dukovany NPP.
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The Proposal of Electrical Maintenance Downtime Elimination
Novotný, František ; Pacas, Radek (referee) ; Videcká, Zdeňka (advisor)
This thesis is focused on description, analysis and minimization of downtime periods related to electricity maintenance activities. In theoretical part various kinds of wasting are described, which can happen during the work of electrician. In the plant Ventily the most faulty machines were found out from analysis of records and appropriate solutions were proposed. In addition to this consecutive company profits were evaluated.
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Creating real-time IMS application
Novotný, Filip ; Mácha, Tomáš (referee) ; Nagy, Ľuboš (advisor)
This paper presents a description of the IP Multimedia Subsystem (IMS) architecture and IMS services. IMS is a standardized next-generation networking architectural framework providing advanced services on mobile and fixed networks. The first chapter describes four-layer IMS architecture and also mentions supported services. The second chapter deals with IMS protocols and primarily focuses on the SIP signaling protocol. UDP, RTP and TLS protocols are also included in this chapter. The third chapter is dedicated to practical part of this paper. A VoIP Java application has been created based on the findings gained throughout the thesis. The main part of the created application consists of client-side application, database MySQL and Servlet application for communication between database and client-side application. The whole system was created using SDS Sony Ericsson 4.1. FD1. An OpenIC lite client has been tested during development on our system and results were compared with created client-side application. A web application based on PHP, MySQL and ActionScript then handles administration and monitoring of customers using voice services.
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PWR fuel assembly model
Cekl, Jakub ; Novotný, Filip (referee) ; Vojáčková, Jitka (advisor)
PWR, fuel assembly, benchmark, burnup, lattice, SCALE, Polaris, validation, reactivity
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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.
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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.
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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.
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Safety of the fuel stored in water pool
Mičian, Peter ; Novotný, Filip (referee) ; Foral, Štěpán (advisor)
This diploma thesis deals with storing the spent nuclear fuel and reviewing its safety. The theoretical part analyzes the processes taking place while the fuel is being used, such as fission, isotopic changes, fission gas release, cracking, swelling and densification of fuel pellet. The thesis is also focused on handling the spent fuel and on the way it makes from the reactor, through the spent fuel pool, the transportation, various kinds of storing, till the reprocessing and final deep geological repository. Furthermore, this part of the thesis briefly discusses computing code MCNP, its main characteristics, input files and using. The practical part of the work is focused on creating the model of the spent fuel pool located next to the nuclear reactor WWER 440/V213. This type was chosen, because it is the most used type of nuclear reactor in Czech Republic and Slovakia. With the help of the code MCNP, the multiplication factor of the main configurations of the fuel in the pool was calculated, and then the required safety regulations to ensure sufficient subcriticality, so its safety, were checked. Next, several analysis were performed using this model. These analyses were concerning the temperature of coolant, fuel and the use of various nuclear data libraries. In the future this model can be used to realize new analyses with new kinds of fuels, materials and data libraries.
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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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Security of VoIP protocols
Novotný, František ; Číka, Petr (referee) ; Krajsa, Ondřej (advisor)
This bachelor dissertation deals with the VoIP (Voice over Internet Protocol) safety. The most used transport and signal protocols employing this technology are presented first. Two extended protocols, SIP (Session Initiation Protocol) and IAX (Inter-Asterisk eXchange Protocol), as well as open source Asterisk, which is closely connected with these protocols, are shown in detail. After that, methods, attacks and threats able to assure secure transfer in the use of VoIP among users are described. Afterwards the practical part of this essay, divided into two parts, is presented. In the first part, a passive attack in the form of tapping is demonstrated, and in the second, active attacks are described which take the form of forced cancellations and forwarded calls between two communicating users. With both attacks, safety measures that could effectively prevent against their potential attacking are proposed. In the closing part, the VoIP safety is evaluated for securing a quality connection between users communicating through it.
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