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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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