PristupačnostReaktorska analiza
Data is displayed for the academic year: 2024./2025.
Course Description
Neutron transport equation and numerical solution methods. Neutron diffusion model of nuclear reactor and criticality calculations. Nuclear reactor kinetics equations. The multigroup diffusion theory and applications. Calculation models for fast and thermal neutron spectrum. Cell calculations for heterogeneous fuel of a reactor. Nuclear reactor core design. Simulation of fuel burnup and nuclear reactor cycle.
Study Programmes
Postgraduate doctoral study programme
General
ID 271554
Summer semester
6 ECTS