Nuclear Reactors: Multigroup Theory

Related lectures (32)

Page 3 of 4

Explores nuclear fission, energy release, fission neutrons, and practical fuels in a nuclear reactor.

Covers the transport of neutrons, scalar neutron flux, neutron currents, and more, along with fuel cycles and types of nuclear reactors.

Covers reactor kinetics, point kinetics equations, numerical solutions, and heterogeneous lattice effects.

Covers neutron slowing down, elastic collisions, and energy loss in a nuclear reactor.

Explores gas-cooled nuclear reactors, covering basic principles, reactor concepts, fuel types, and advanced technologies.

Explores the practical approach of homogenizing reactor core analysis and the calculation route for multigroup diffusion equations.

Explores neutron detection in reactors, focusing on MiMi detectors and their applications in high-resolution experiments.

Covers the formalism and criticality analysis of nuclear reactors, focusing on mathematical equations and reactor stability.

Explores energy release from fission, fuel burnup, and fission fragments yields and decay in a nuclear reactor.

Explores the impact of burnup on neutronics in nuclear reactors, focusing on fissioning isotopes and fission product poisons.