Covers the solutions of neutron diffusion, including analytical solutions, Laplacian in different geometries, and the physical significance of the diffusion area.
Explores neutron moderation, absorption, resonance scattering, and energy discretization in reactors, emphasizing the trade-offs between computational efficiency and accuracy.
Explores breeding and liquid metal fast reactors, focusing on the challenges of managing plutonium, transmutation to reduce nuclear waste, and the use of liquid metal cooling for reactor efficiency and safety.
Analyzes the total cross section data for nuclear fission, covering energy dependence, transport, reactions, uncertainties, fission fragments, and radiological hazards.
