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Selected ČSN Road Design Elements Optimization
Stránský, Jakub ; Čepil, Jiří (referee) ; Kosňovský, Michal (advisor)
The master‘s thesis focuses on the optimization of the design values of curves of the horizontal alignments of the roads. It deals with the comparison of values between czech and foreign standards and differences between them. The practical part examines the values of the real speeds of vehicles passing through the curves of various parameters that were measured during measurements of selected curves during 2014. From these data a new design values are derived that could be used for the design of horizontal alignments.
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Evaluation of Nuclear Fuel Safety and Reliability Using Research Reactors' In-Core Experiments
Matocha, Vítězslav ; Foral, Štěpán (referee) ; Katovský, Karel (advisor)
The aim of this master thesis is to show a connection among nuclear fuel safety, experiments led in research reactors and calculation codes. This thesis focuses on the calculation code Transuranus. There are represented four experiments, which were calculated in Transuranus. The fission gas release, elongation and growth of fuel were particularly monitored. Is is possible to set differences among versions v1m1j09 and v1m3j12 from achieved results, as well as the influence of selected Transuranus parameters on the results, so the thesis may bring new pieces of knowledge for improvement of safety analysis calculation by Transuranus.
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Selected ČSN Road Design Elements Optimization
Stránský, Jakub ; Čepil, Jiří (referee) ; Kosňovský, Michal (advisor)
The master‘s thesis focuses on the optimization of the design values of curves of the horizontal alignments of the roads. It deals with the comparison of values between czech and foreign standards and differences between them. The practical part examines the values of the real speeds of vehicles passing through the curves of various parameters that were measured during measurements of selected curves during 2014. From these data a new design values are derived that could be used for the design of horizontal alignments.
|
|
|
Evaluation of Nuclear Fuel Safety and Reliability Using Research Reactors' In-Core Experiments
Matocha, Vítězslav ; Foral, Štěpán (referee) ; Katovský, Karel (advisor)
The aim of this master thesis is to show a connection among nuclear fuel safety, experiments led in research reactors and calculation codes. This thesis focuses on the calculation code Transuranus. There are represented four experiments, which were calculated in Transuranus. The fission gas release, elongation and growth of fuel were particularly monitored. Is is possible to set differences among versions v1m1j09 and v1m3j12 from achieved results, as well as the influence of selected Transuranus parameters on the results, so the thesis may bring new pieces of knowledge for improvement of safety analysis calculation by Transuranus.
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