Diffusion of Neutrons - Part IICovers the review of the diffusion equation and its analytical solutions for simple cases, along with the physical significance of the diffusion area.
Diffusion of NeutronsExplores Fick's law, neutron balance, scattering, and diffusion length in the context of neutron diffusion.
Diffusion of NeutronsCovers analytical solutions for neutron diffusion from planar sources in different media.
Diffusion: Macroscopic ViewExplores diffusion from a macroscopic perspective, emphasizing the derivation of the diffusion equation through mass conservation and fixed flux law.
Diffusion EquationExplores the diffusion equation, flux, diffusivity, Fick's Law, boundary conditions, and concentration-dependent diffusion coefficient.
Heterogeneous ReactorsCovers the analysis of heterogeneous reactors, focusing on the multiregion reactor, one-group method, and criticality conditions.
Diffusion of NeutronsExplores neutron diffusion, eigenfunctions, elastic collisions, and typical values, culminating in a summary of the diffusion area and length.
Neutron Diffusion ModelingExplores neutron diffusion in nuclear reactors, emphasizing key concepts for modeling neutron behavior and reactor safety.
Multigroup theoryCovers the multigroup theory, focusing on the two-group method and resonance escape probability.
