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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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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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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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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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