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Boltzmann equation eigenvalue calculation for nuclear reactor cores, spent fuel pools, and storage casks
 Bílý, Lukáš ; Vojáčková, Jitka (referee) ; Katovský, Karel (advisor)
In my thesis, I focus on the computational tool SCALE, which utilizes computational codes for modeling and calculating critical values of reactors. Prior to the practical section, there is a theoretical part that focuses on reactor physics and computational codes. The selected computational code is the KENO V.a code, which employs the Monte Carlo method for calculating the effective multiplication coefficient. The computational code is used for modeling selected benchmarks from the ICSBEP database. At the end of the thesis, the average percentage deviation will be determined.
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