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Zhodnocení termomechanického chování perspektivních jaderných paliv při havárii s vnosem reaktivity / Assessment of the thermomechanical behaviour of perspective nuclear fuel for reactivity insertion accidents

The objective of this master’s thesis is to simulate thermo-mechanical behaviour of nuclear fuel in a pressurized water reactor during a reactivity initiated accident. An important part of this work is focused on examination of processes which occur during such accident and on creation of a detailed overview of material properties of nuclear fuel and fuel cladding which are necessary for simulations that closely reflect reality. Simulations in this thesis examine cases of fresh or irradiated nuclear fuel for two types of fuel cladding, Zircaloy-4, a material that is currently used in nuclear reactors, and ceramic matrix composite material made of SiC. The thesis also presents comparison of results with a corresponding international benchmark and an assessment of the influence of selected input parameters on obtained results.

Identiferoai:union.ndltd.org:nusl.cz/oai:invenio.nusl.cz:242902
Date January 2016
CreatorsHalabuk, Dávid
ContributorsSuk, Ladislav, Martinec, Jiří
PublisherVysoké učení technické v Brně. Fakulta strojního inženýrství
Source SetsCzech ETDs
LanguageCzech
Detected LanguageEnglish
Typeinfo:eu-repo/semantics/masterThesis
Rightsinfo:eu-repo/semantics/restrictedAccess

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