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Explores the impact of burnup on neutronics in nuclear reactors, focusing on fissioning isotopes and fission product poisons.
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.
Covers the review of the diffusion equation and its analytical solutions for simple cases, along with the physical significance of the diffusion area.
Covers neutron depletion in nuclear reactors and its mathematical models and calculations.
Discusses the physical significance of neutron diffusion and analytical solutions for a point source.
Covers the solutions of neutron diffusion, including analytical solutions, Laplacian in different geometries, and the physical significance of the diffusion area.
Explores slowing down equations, lethargy, and Fermi age theory in neutron moderation.
Covers analytical solutions for neutron diffusion from planar sources in different media.
Explores burnup algorithms, time-step discretization, LWR fuel evolution, spent fuel composition, refueling techniques, and boric acid control in PWRs.
