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Design concept of the facility for the educational objectives of the boiling crisis
Vojáčková, Jitka ; Škorpík, Jiří (referee) ; Martinec, Jiří (advisor)
This thesis deals with a design concept of the facility for the educational objectives of the boiling crisis. In the first part, the issue of boiling crisis is explained. There are also examples of some experimental facilities in the world. The second part includes design concept of a loop, which is accompanied by designs of individual devices, such as separator, condenser, exchanger, pump, water tank, electric heater. The thesis also states designs of throttle control, temperature control and flow control.
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Subchannel analysis of VVER-100 reactor core
Bednář, Michal ; Petrosyan, Taron (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with boiling crisis and with departure from nucleate boiling ratio. This thesis explains terms like the boiling crisis in nuclear reactors and the thesis deals with individual parameters of the reactor core, which have an impact on departure from nucleate boiling ratio. After that, the thesis deals with subchannel analysis and describes basic mathematical and physical models of the chosen subchannel program. The thesis then processes, with the ALTHAMC12 subchannel program, the chosen parameters and their impact on departure from nucleate boiling ratio. The conclusion of the diploma thesis deals with the evaluation of the best and worst calculated combination.
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Experiments critical heat flux
Štaffa, Petr ; Martinec, Jiří (referee) ; Suk, Ladislav (advisor)
The Bachelor’s thesis deals with phenomenon of critical heat flux in a core of nuclear reactor. The first part is dedicated to describe physical nature of critical heat flux and basic thermo mechanical and hydrodynamics terms. The second part is dedicated to summarize experimental investigations on critical heat flux and their process.
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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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Experimental and calculational analyses of new generation nuclear fuels
Tioka, Jakub ; Mičian, Peter (referee) ; Števanka, Kamil (advisor)
The search for Accident tolerant fuels (ATF) which is the first part of this thesis is currently one of the most actual topics in the field of nuclear fuels. These fuels must be first successfully tested in operational and also accident conditions for their possible inclusion in commercial use. Following part of the thesis specifically focuses on the boiling crisis in nuclear reactors which can damage the nuclear fuel cladding. Therefore, it is necessary to know the critical heat flux value and the departure from nuclear boiling ratio. Calculations which determine critical heal flux value are placed in the practical part of the thesis. Calculations are compared with the data obtained during experiments. The ALTHAMC12 and the other correlations which are based on the previous measurements are used for the computational analysis.
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Experimental and calculational analyses of new generation nuclear fuels
Tioka, Jakub ; Mičian, Peter (referee) ; Števanka, Kamil (advisor)
The search for Accident tolerant fuels (ATF) which is the first part of this thesis is currently one of the most actual topics in the field of nuclear fuels. These fuels must be first successfully tested in operational and also accident conditions for their possible inclusion in commercial use. Following part of the thesis specifically focuses on the boiling crisis in nuclear reactors which can damage the nuclear fuel cladding. Therefore, it is necessary to know the critical heat flux value and the departure from nuclear boiling ratio. Calculations which determine critical heal flux value are placed in the practical part of the thesis. Calculations are compared with the data obtained during experiments. The ALTHAMC12 and the other correlations which are based on the previous measurements are used for the computational analysis.
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Subchannel analysis of VVER-100 reactor core
Bednář, Michal ; Petrosyan, Taron (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with boiling crisis and with departure from nucleate boiling ratio. This thesis explains terms like the boiling crisis in nuclear reactors and the thesis deals with individual parameters of the reactor core, which have an impact on departure from nucleate boiling ratio. After that, the thesis deals with subchannel analysis and describes basic mathematical and physical models of the chosen subchannel program. The thesis then processes, with the ALTHAMC12 subchannel program, the chosen parameters and their impact on departure from nucleate boiling ratio. The conclusion of the diploma thesis deals with the evaluation of the best and worst calculated combination.
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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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