Concept
Thermal-neutron reactor
Related lectures (35)
Neutron Moderation with Absorption
Covers neutron moderation with absorption, including treatment of resonances, temperature effect, and neutron spectra.
Neutron Slowing Down in Reactors
Explores neutron slowing down in reactors, emphasizing the transition from high-energy to thermal neutrons and the role of moderators like hydrogen and graphite.
Resonance Escape Probability Derivation
Explains the derivation of resonance escape probability for neutrons slowing down without being captured.
Neutron moderation
Covers neutron slowing down, elastic collisions, and energy loss in a nuclear reactor.
Multiplying media: Analytical Solutions and Non-leakage Probability
Covers media containing fuel, analytical solutions, and non-leakage probability for thermal and fast neutrons.
Neutron Diffusion Equation: Numerical Methods
Covers numerical methods for solving the neutron diffusion equation and addressing heterogeneous effects in thermal reactors.
Modified One Group Theory: Media Containing Fuel
Explores the modified one group theory for thermal reactors, focusing on media containing fuel and resonance treatment.
Nuclear Fission: Energy Release and Neutron Interactions
Explores nuclear fission, energy release, fission neutrons, and practical fuels in a nuclear reactor.
Nuclear Reactivity: Moderation, Enrichment, Absorption
Covers moderation, enrichment, and absorption in nuclear reactivity.
Introduction to Nuclear Engineering
Introduces nuclear engineering, covering reactor types, components, and thermodynamics, including pressurized water reactors and boiling water reactors.