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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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Investigation of Nuclear Power-Reactor Core Poisoning
Janošek, Radek ; ČR,, Milan Štefánik, Ústav jaderné fyziky AV (referee) ; Katovský, Karel (advisor)
The aim of this Bachelor´s Thesis is to characterize fundamental transient processes, which takes place in nuclear power-reactor. The main goal is the theoretical analysis of these processes, which include xenon poisoning, samarium poisoning, xenon after shutdown, xenon oscillation, and permanent poisoning. A significant part of the thesis deal with the simulation of xenon poisoning and samarium poisoning. Model was created using Maple software. One of the other points is to state the basic concepts of nuclear physics and also to describe nuclear power-reactor primary operating processes.
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Boltzmann equation eigenvalue calculation for nuclear reactor cores, spent fuel pools, and storage casks
Bílý, Lukáš ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
In my thesis, I focus on the computational tool SCALE, which utilizes computational codes for modeling and calculating critical values of reactors. Prior to the practical section, there is a theoretical part that focuses on reactor physics and computational codes. The selected computational code is the KENO V.a code, which employs the Monte Carlo method for calculating the effective multiplication coefficient. The computational code is used for modeling selected benchmarks from the ICSBEP database. At the end of the thesis, the average percentage deviation will be determined.
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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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|
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Investigation of Nuclear Power-Reactor Core Poisoning
Janošek, Radek ; ČR,, Milan Štefánik, Ústav jaderné fyziky AV (referee) ; Katovský, Karel (advisor)
The aim of this Bachelor´s Thesis is to characterize fundamental transient processes, which takes place in nuclear power-reactor. The main goal is the theoretical analysis of these processes, which include xenon poisoning, samarium poisoning, xenon after shutdown, xenon oscillation, and permanent poisoning. A significant part of the thesis deal with the simulation of xenon poisoning and samarium poisoning. Model was created using Maple software. One of the other points is to state the basic concepts of nuclear physics and also to describe nuclear power-reactor primary operating processes.
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