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Accident Tolerant Fuel simulation loaded in advanced nuclear reactor during severe accident conditions
Hamřík, Lukáš ; Foral, Štěpán (oponent) ; Mičian, Peter (vedoucí práce)
This diploma thesis introduces accident tolerant fuels that are considered to be a next step in increase of safety margins of nuclear power plants. In the beginning, the weaknesses of the currently operated fuel system are exposed. Accident-tolerant fuel options and their categories are described in their stages of development and faced issues before their deployment. The APR1400 plant with its accident mitigation systems is mentioned, the plant model is used to assess the impact of advanced cladding materials in a plant undergoing severe accident. The MELCOR code, capable of simulations of severe accident phenomena, is briefly introduced with its capabilities. The implementation of advanced cladding materials to MELCOR is described, altogether with simulated scenarios. In the end, the results obtained from the simulations are discussed.
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Subchannel model of APR1400 reactor core
Kazimov, Nurmet ; Števanka, Kamil (oponent) ; Foral, Štěpán (vedoucí práce)
The master thesis describes the subchannel analysis methodology. Subchannel analysis serves as a valuable tool in evaluating the safety of nuclear reactor operations. The results obtained from subchannel analysis provide vital information for assessing risks associated with boiling crises, as well as evaluating the effectiveness of moderation and fuel rod plutonium production. To achieve this, it is imperative to develop and validate an active zone model within the subchannel code. The master thesis deals with this procedure in the case of the active zone of the APR1400 reactor. The results are compared with experimental data and other simulation results to validate the accuracy of the model.
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Ukázkový výpočet rezervy do krize varu
Křeček, Tomáš ; Števanka, Kamil (oponent) ; Foral, Štěpán (vedoucí práce)
Tato diplomová práce se zabývá problematikou rezervy do krize varu v jaderném reaktoru APR1400. Nejdříve je popsána konstrukce reaktoru, zejména aktivní zóna a palivové soubory. Práce se poté věnuje vysvětlení problematiky krize varu v jaderných reaktorech. Hlavním cílem práce je vytvoření a validace modelu aktivní zóny reaktoru APR1400 v subkanálovém programu ALTHAMC12. Vytvořený model je validován porovnáním s referenční studií a v neposlední řadě se práce věnuje ukázkovému výpočtu rezervy do krize varu pomocí poskytnutých dat firmou TES s.r.o.
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