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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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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.
|
|
|
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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