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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.
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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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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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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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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.
|
|
|
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.
|
|
|
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.
|
|
|
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.
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