Covers the solutions of neutron diffusion, including analytical solutions, Laplacian in different geometries, and the physical significance of the diffusion area.
Covers analytical solutions for neutron diffusion from planar sources in different media.
Covers the multigroup theory, focusing on the two-group method and resonance escape probability.
Covers neutron slowing down, elastic collisions, energy loss, equations, lethargy, and Fermi age theory.
Explores Fick's law, neutron balance, scattering, and diffusion length in the context of neutron diffusion.
Explores neutron diffusion, eigenfunctions, elastic collisions, and typical values, culminating in a summary of the diffusion area and length.
Explores the diffusion equation, flux, diffusivity, Fick's Law, boundary conditions, and concentration-dependent diffusion coefficient.
Covers the analysis of heterogeneous reactors, focusing on the multiregion reactor, one-group method, and criticality conditions.
Explores diffusion from a macroscopic perspective, emphasizing the derivation of the diffusion equation through mass conservation and fixed flux law.
Explores the historical development and industrial applications of radiography and computerized tomography with X-rays, gammas, and neutrons.
