This graduation thesis deals with evaluation of power and coolant flow in reactor core. The first part is a description of nuclear power plant VVER 440. It is focused on parts important for transfer and utilize energy in regular operating of generating block. In the second part, the equations for calculation of power and coolant flow in reactor core are deduced. The last part is about designing the program for calculation of published values. There are specified requirements for the program and on the basis of this the source code is written. The parts of code are described. In conclusion of this part, the user's manual is work out. The program is on CD in the annexe.
| Identifer | oai:union.ndltd.org:nusl.cz/oai:invenio.nusl.cz:228896 |
| Date | January 2010 |
| Creators | Tvrdý, Miloslav |
| Contributors | Šen, Hugo, Nerud, Pavel |
| 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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