The submitted master thesis deals with finding the right combination of models describing the cladding behavior implemented in the FEMAXI-6 computational code and then comparing it with the benchmark Zaporoshye, Novovoronezh and the modified FERMAXI 6 program with implemented models describing the E110 behavior used for VVER-type reactor fuel rods. Initially, there is a description of the FEMAXI-6 nuclear fuel analysis program including its structure, calculation mechanics and input file description. Furthermore, the work presents the benchmarks used to evaluate individual combinations of fuel models. An important part is the description of the PIE measurement, including measurement uncertainty, which can affect the results of the work. The next chapter contains a description of what affects fuel behavior during irradiation, which can be mathematically expressed and modeled. The following chapter describes the material equations defining the E110 alloy used as cladding of the fuel rods and which were subsequently implemented into the FEMAXI-6 computing program. The last chapter is devoted to the description of the results with appropriate comments.
Identifer | oai:union.ndltd.org:nusl.cz/oai:invenio.nusl.cz:400560 |
Date | January 2019 |
Creators | Čásar, Ondřej |
Contributors | Katovský, Karel, Foral, Štěpán |
Publisher | Vysoké učení technické v Brně. Fakulta elektrotechniky a komunikačních technologií |
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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