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Design modification of the collimator for RAW measuring system
Svoboda, Štěpán ; Lisý, Martin (referee) ; Šen, Hugo (advisor)
This thesis deals with structural design of collimator. Collimator is important component of radioactivity measuring device. This apparatus is made by Envinet. Collimator is part of device, which makes good conditions for measuring radioactivity, protects detector and tries avoid overload detector. In this thesis is dealt simplification of collimator. It supposed, that simplified collimator will be more reliable. This proposal saves more money, because company will not have to send employee of Envinet to service their measuring devices in a very distant countries, such as Russia, Ukraine etc.
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Engineering design of the Freeze Valve
Zeman, Radek ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This bachelor´s thesis deals with practical design of freeze valve for nuclear facilities from both calculation and construction point of view. Firstly, a brief analysis of technologies of fast neutron reactors and reactors with fuel dissolved in melted fluorine salts has been done. The author points out the advantages of their use that may result in becoming an important part of nuclear power engineering. Working fluids are taken from these reactors – liquid sodium and mixture of molten salts NaBF4-NaF. The author deals with choice of suitable construction materials and ways of heat-transfer from working fluid. Secondly, several construction solutions have been assessed and project documentation has been created for some of them. These designs include alternative shapes of valves and canals, where heat exchanging medium flows – Field tube and valve with helix canal. These concepts allow fast intake (conducting away) of heat into the working fluid and after verification on an experimental stand these valves could work in conditions of nuclear facilities. Times of cooling and heating for chosen designs and working fluids are calculated by previously derived dimensionless equations describing transient heat-transfer field with phase change supposing low Biot numbers.
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Fuel elements thermal field analysis
Vacek, Jiří ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
The purpose of this thesis is to describe calculation procedures of fuel element thermal field analysis. The next is VVER-440 fuel element solution for selected operating conditions. These solutions are also made numerically with ANSYS. The importance of each effect on solution is assessed in thesis. The possibilities of some simplifications are also assessed.
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Improving of reliability for NPP
Dubovský, Dávid ; Šen, Hugo (referee) ; Nerud, Pavel (advisor)
The aim of this paper is to describe and evaluate the reliability of nuclear plants at Bohunice (EBO). Then illuminate the methods for increasing the reliability and specify one of them (INPO AP 913). After describing the methods, summarize the work results of this method and proposes the way of application.
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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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Character of nuclear energy in European Union - history and present
Koryčanský, Roman ; Šen, Hugo (referee) ; Martinec, Jiří (advisor)
The thesis deals with the development and current status of nuclear energy in Europe. The first part focuses on the legislative background in the EU – The Euratom treaty. Next, the thesis describes the history of European companies that are engaged in nuclear energy, in particular the French company AREVA. The largest part of the thesis deals with the relationship of nuclear energy and public opinion, and focuses on the status of nuclear energy in selected countries and the attitudes of environmental organizations. This section also includes a description of the history of the most serious accidents. The conclusion focuses on the economic aspects of nuclear energy and its future.
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Nuclear safety and inspection authorities
Dvořák, Aleš ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
The bachelor thesis deals with nuclear safety. The target of it is to convince regular people, that nuclear power plants are safe for them as well as for the enviroment. Thesis describes the supervisory authority, which oversees the safe operation of nuclear power plants. You find out about improvements in safety features in future projects. You can obtain information about possible stress of materials used in nuclear power plant, radioactive waste and impact of dangerous radionuclids on enviroment. The theses clearly shows that the claims on nuclear safety aren’t constant, but they have increasing trend during the time.
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Inspection authorities of nuclear safety in the world and their purpose
Dvořák, Aleš ; Nerud, Pavel (referee) ; Šen, Hugo (advisor)
This thesis deals with issues of nuclear safety. The first section provides an overview of international organizations and associations, which control via their activities all regulations concerning nuclear safety, the technical state of equipments and systems in nuclear power plants. The second part deals with technical description of important equipment and systems of the nuclear powerplants at chosen nuclear reactors of II. and III. generation. The last part explains the conception of nuclear safety deeply. The reader can gain a deep overview of the different levels of protection and attention is also paid to the methods that contribute to the evaluation of nuclear safety.
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Intermediate heat exchanger natrium - natrium
Kupčík, Petr ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This paper deals with intermediate heat exchangers in nuclear power plants. First section of this paper is devoted to analysis and divide of construction designs of intermediate heat exchangers in commercial and experimental power plants. There is a description of thermal, hydraulic and strength calculations during projection of IHX in the second chapter. There has been made a blueprint of loop type IHX in the final chapter of this paper.
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