Lecture
This lecture covers the behavior of neutrons in reactors, focusing on heterogeneous lattices and group constant determination. It discusses spatial self-shielding, neutron escape mechanisms, and the impact of lattice heterogeneities on reactor physics. The instructor explains the practical approaches to reactor core analysis, including spatial homogenization and the generation of few-group macroscopic cross sections. Additionally, the lecture delves into the physical significance of parameters like neutron lifetime and delayed neutrons in reactor kinetics. The session concludes with an overview of the computational schemes used for practical reactor calculations, involving transport and diffusion theories.