The thesis deals with a project of a steam generator heated with liquid sodium. The first section describes some types of steam generators at nuclear power plants which have been projected or put into use. The next part presents a draft concept of the steam generator, solved by this work. The implementation of the steam generator module has been selected from several options, based on the thermal, hydraulic and stress calculations and on the chosen criteria. The conclusion of this thesis deals with the evaluation of the final solution in terms of nuclear safety and technical solutions, and compares this solution to similar projects following various criteria.
| Identifer | oai:union.ndltd.org:nusl.cz/oai:invenio.nusl.cz:229195 |
| Date | January 2010 |
| Creators | Kaláb, Ctibor |
| Contributors | Šimo, Tomáš, Matal, Oldřich |
| 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 |
Page generated in 0.0018 seconds