|
|
Software for teaching the control of a nuclear power plant steam generator
Toman, Jiří ; Nekula, Pavel (referee) ; Němec, Zdeněk (advisor)
This diploma thesis deals with the study of steam generator regulation and development of an application, which includes a real simulation of steam generator water level control with its graphical interpretation. It presents analysis and solution in the form of software that will be a valuable application in practice. The result of the diploma thesis is educational software simulating the behavior of the steam generator level control system in referenced nuclear power plant.
|
|
| |
|
|
Trasfer Heat Analysis in Steam Generators in blocks of VVER 440
Roupec, Petr ; Pulec, Jiří (referee) ; Šen, Hugo (advisor)
The aim of this thesis is to analyze the heat transfer in steam generator of blocks in the nuclear power plant VVER 440. The steam generator represents the border between the primary and the secondary circuit. The heat is carried from a warm water from reactor to a cold water. The steam arises after the heat transfer and drives the steam turbine. An important quantity which represents the heat transfer is a heat transfer factor. This thesis is divided into theoretical and a practical part. In the theoretical part is mentioned a principle of the steam generator and the theoretical calculation of the heat transfer factor, which comes first of all from the character of the streaming in the steam generator. The practical part brings a comparison of the heat transfer factor calculated from data measured after the start of the third block of EDU in 1986, with the heat transfer factor which comes from the measurement after the power-increase for 105 % of nominal power of the same block in 2009. Further is shown the prediction of the heat transfer factor for next power-increase and the following service is shown too.
|
|
|
Design of Electric Iron
Jakubec, Jakub ; Buganská, Tamara (referee) ; Křenek, Ladislav (advisor)
The subject of my bachelor’s thesis is create elegant and timeless design of electric iron for home or semi-professional use in accordance with the technical, ergonomic and aesthetic requirements. The aim is create the product which would be unusual, interesting and easy to use.
|
|
|
Design of the steam generator for modular reactor
Černý, Marian ; Baláš, Marek (referee) ; Šen, Hugo (advisor)
Subject of this thesis is design of the steam generator for modular reactor. The dissertation consist of the theoretical part, where are described heat-exchangers and steam generators used in nuclear power plants. Second part contains theoretical calculations in the first approach (thermal, hydraulic and strenght calculation). In the next part are particular variants of steam generator selected. For the final variant are necessary calculations (introduced above) and drawings of selected parts are done. In the final statement is technical solution evaluated, and the parameters of the steam generator are compared with actually used steam generators.
|
|
|
The heat dissipation efficiency of the steam generator Dukovany at low water levels
Veselý, Jakub ; Šnajdárek, Ladislav (referee) ; Pospíšil, Jiří (advisor)
The goal of this thesis is to simulate the course of events during Dukovany Nuclear Power Plant blackout and to determine the optimal process of cooling down the cold branches of the primary circuit loops to secure the maximum amount of the primary fuel needed for the residual heat outlet so that the operating staff has as much time as possible for renewing the electric power supply. The first part of the thesis describes nuclear power plants built in the Czech Republic and in the world as well as reactor blocks whose construction is being considered. The detailed description of Dukovany’s steam generator is shared in chapter three. Following chapter summarizes blackouts that occurred at power plants around the world, events that might have led to blackouts in the Czech Republic, and it also describes current approach to blackout problematics at Dukovany Nuclear Power Plant. Chapters six and seven contain the core of the thesis. That includes detailed description of a mathematical model explaining the behaviour of a reactor block during blackout as well as the analysis of the results found.
|
|
|
Steam generator heated with liquid sodium
Kóša, Štefan ; Bogdálek, Jan (referee) ; Šen, Hugo (advisor)
This bachelor’s thesis is concerned with engeneering a steam generator (secondary heat exchanger) for a fast breeder reactor. It includes proposal of the projected type, thermal, hydraulic and strenght calculation, and examination of a proposal in light of nuclear safety. It contains a lay-out of selected parts.
|
|
|
Calculation of Parameters of Secondary Circuit of Nuclear Power Plant
Vaněček, Lukáš ; Lázničková, Ilona (referee) ; Raček, Jiří (advisor)
The contents of this thesis is a suggestion of calculation and follow-up calculation of parameters of secondary circuit of assigned thermal diagram and parameters of a nuclear power plant. The thesis also includes possibilities of making nuclear circulations. Part one of the thesis briefly describes possibilities of making nuclear circulations, types of nuclear energy reactors, types of steam generators and types of turbines used in nuclear power plants. The second part of the thesis includes a suggestion of calculation for the real thermal diagram of secondary circuit of nuclear power plant. The attention in this calculation is given to expansion of steam in a turbine, determining parameters of mass in a circuit, calculation of steam demanded and determining power and efficiency of nuclear power plant. The final part of the thesis is a calculation of parameters of secondary circuit of nuclear power plant for given values and evaluation of results of calculation.
|
|
|
Condenser design of a nuclear power plant
Hejduk, Michal ; Šnajdárek, Ladislav (referee) ; Milčák, Pavel (advisor)
The topic of this master´s thesis is the design of the steam generator for a nuclear power plant with VVER 440 reactor. The first part of this thesis describes a brief history of nuclear research, which is followed by an overview of nuclear reactors used now. The next part deals the types of steam the types of steam generators used today with their basic elements and design recommendations. The last and final part is the design of a steam generator for nuclear power plant with a VVER 440 reactor. Above all, is the thermal calculation of the steam generator and behaviour of steam generator depending on the reactor power. The design solution of steam generator and its strength calculation. The last part of the steam generator calculation the pressure loss of the steam generator is investigated.
|
|
|
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.
|
guest ::
