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The flange gasket modification of SG VVER 440 primary collector
Blažková, Eva ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
The aim of this thesis is to address issues concerning the sealing of the lid for the primary collector within the steam generator (SG) of the nuclear power plant VVER 440. These steam generators are sealed in the original design by nickel rings. Modifying the existing method of sealing by a new type of sealing material, primarily from expanded graphite, can significantly reduce the pressure in the sealing surface and also stress in bolts and flanged joints. The new solution of sealing between the joint of collector and the lid should extend the life of joints and thus the nuclear and technical safety. The text is divided into the theoretical and computational part. A principle of the SG, the SG design, and a description of the joint and lid are mentioned in the theoretical part. The computational part shows calculations of the new joint, the original one, and comparison of both solutions in terms of technical and nuclear safety. The work contains drawing of the new joint.
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Upgrading the secondary circuit of the Dukovany NPP
Fialová, Michaela ; Fiedler, Jan (referee) ; Šen, Hugo (advisor)
With the ever increasing usage of electric power and decreasing supply of natural resources, there is a growing effort to effectivelly maximise current dispositions of resources. Utilising project reserves at already functioning Nuclear powerplants belongs to these projects. In this article I am going to describe this utilisation and overall modernisation of the Dukovany Nuclear powerplant.
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CFD analysis of thermal stress of a tubesheet
Vince, Tomáš ; Babička Fialová, Dominika (referee) ; Rebej, Miroslav (advisor)
This diploma thesis focuses on the phenomena of multiphase flow in a steam generator as a one of probable causes of tubes and tubesheet weld cracking. In the first part of the work, a research was carried out focusing on the boiling and the phenomenon of two-phase flow in technical applications, its characteristics and properties. The thesis continuous with an overview of available numerical multiphase models in the ANSYS Fluent 2021 R1 and a research of previously published works focused on two-phase flow with the presence of boiling. The research is followed by a description of the particular boiler, which is part of the nitric acid production plant in the chemical company DUSLO, a.s., its operating conditions and a more detailed description of the issue that is being addressed in this thesis. The second part of the work continuous with a description of the computational model, including a description of the geometry of the model and used simplifications, the computational mesh and the description of boundary conditions. Important part is the description of calculation setting of steady-state and transient CFD simulations in ANSYS Fluent. Finally, the results of the two-phase flow calculation are presented and then discussed in the conclusions.
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The steam generator for ESFR reactor
Bátěk, David ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This master thesis deals steam generator for ESFR (European Sodium Fast Reactor), which is heated by liquid sodium. In the beginning chapters, there are theoretic information about ESFR's parameters and its' comparison with ohter types of heat exchangers in nuclear reactors with the same principal (sodium as a coolant). Then designing part follows, which contents of introduction of calculations, option of material and conception of heater. Computational part on its own includes thermal, hydraulic and stress calculations and comparison with aspects in nuclear safety and security.
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The feedwater safety valve flow capacity analysis
Fialová, Michaela ; Lisý, Martin (referee) ; Šen, Hugo (advisor)
In this thesis I review the sufficient flow capacity of the safety valve against high-pressure heater thermal pressurization in high-pressure feedwater heater on nuclear power Dukovany. I present basic possible cases of thermal pressurization both a high node heater, and the extended pressure unit in case of closure all power heads to steam generators.
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Sodium steam generator for experimental stand
Janíček, Martin ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This thesis deals with the experimental liquid sodium heated steam generator. The first chapters describe the many aspects that should be taken into account when designing this type of steam generator. Furthermore, is approximated in the proposal the work itself. On the basis of thermal, hydraulic calculation of strength and was chosen one preferred option. In conclusion, the best option is evaluated steam generator sodium-water and the possibility of realization.
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Analysis of the secondary circuit of the VVER 440 block
Černý, Michal ; Kracík, Petr (referee) ; Milčák, Pavel (advisor)
The main aim of this thesis is the model design and control the secondary circuit block VVER 440. The search part of my work is a description of the secondary circuit. In the first part of the calculation is performed for the rated secondary circuit. The second calculation part focuses on the calculation circuit of the secondary for the reduced, influenced by shutting down one steam generator.
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Expressing uncertainty of efficiency value
Kňava, Miroslav ; Pernikář, Jiří (referee) ; Koška, Petr (advisor)
The aim of this work is to analyze the methodology for executing examination heat transfer tubes of steam generator by method of eddy currents on EDU, to create the model for the estimate of standard combined uncertainty of efficiency value, quantify the individual components of standard uncertainties, analyse the influence of different components on the expressing of uncertainty, to make the final estimate of standard combined and enlarged uncertainty of efficiency value and as of minor objective to evaluate the suitability of the use of this method .
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Design modification of heatexchanger for steam generation
Prášek, Radovan ; Gottvald, Jakub (referee) ; Nekvasil, Richard (advisor)
This thesis deals with heat exchangers. Thesis is divided into two parts. First one is devoted to various construction of equipment for heat exchange, basic divisions and overwiew of the types. The second part deals with a specific solution modification of existing equipment. The solution includes a description of the problematic parts, calculation of selected parts, design modifications and basic drawings of the proposed solution.
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