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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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Departure from nucleate boiling in nuclear reactors
Bednář, Michal ; Števanka, Kamil (referee) ; Foral, Štěpán (advisor)
This bachelor thesis deals with problem of boiling crisis in nuclear reactors and how this problem influences working od nuclear reactor. This thesis is focused on power water reactors, with focus on VVER 1000 reactor type, which fuel assembly is described in this thesis in more detail. In this thesis there are described terms related to boiling crisis and two-phase flow regimes. In the last part, the thesis is dedicated to the correlations for the critical condition and individual correlations are compared.
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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.
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Departure from nucleate boiling in nuclear reactors
Bednář, Michal ; Števanka, Kamil (referee) ; Foral, Štěpán (advisor)
This bachelor thesis deals with problem of boiling crisis in nuclear reactors and how this problem influences working od nuclear reactor. This thesis is focused on power water reactors, with focus on VVER 1000 reactor type, which fuel assembly is described in this thesis in more detail. In this thesis there are described terms related to boiling crisis and two-phase flow regimes. In the last part, the thesis is dedicated to the correlations for the critical condition and individual correlations are compared.
|
|
|
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.
|
|
|
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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