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.
Identifer | oai:union.ndltd.org:nusl.cz/oai:invenio.nusl.cz:230440 |
Date | January 2012 |
Creators | Bátěk, David |
Contributors | Martinec, Jiří, Šen, Hugo |
Publisher | Vysoké učení technické v Brně. Fakulta strojního inženýrství |
Source Sets | Czech ETDs |
Language | Czech |
Detected Language | English |
Type | info:eu-repo/semantics/masterThesis |
Rights | info:eu-repo/semantics/restrictedAccess |
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