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Lecture
Neutron moderation
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Related lectures (32)
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Neutron Physics: Reactor Behavior
Covers neutron physics in nuclear reactors, including criticality, fission, and neutron distribution.
Neutron chain-reacting systems
Explores chain reactions, multiplication factor, fuel cycles, reactor design, and types of nuclear reactors, ending with a summary of key concepts.
Neutron Physics: Reactor Overview
Covers neutron interactions, fission products, energy release, and reactor design considerations.
Introduction to Nuclear Engineering: Reactor Kinetics
Introduces reactor kinetics in nuclear engineering, covering reactivity control, critical conditions, moderator materials, and chain reaction control.
Neutron Transport Theory: Fundamentals and Applications
Explores neutron transport theory, scalar neutron flux, and Fick's law in reactor physics.
Multiplying media: Analytical Solutions and Non-leakage Probability
Covers media containing fuel, analytical solutions, and non-leakage probability for thermal and fast neutrons.
Nuclear Fission: Energy Release and Neutron Interactions
Explores nuclear fission, energy release, fission neutrons, and practical fuels in a nuclear reactor.
The Diffusion of Neutrons
Covers the transport of neutrons, scalar neutron flux, neutron currents, and more, along with fuel cycles and types of nuclear reactors.
Nuclear Fission: Total Cross Section Analysis
Analyzes the total cross section data for nuclear fission, covering energy dependence, transport, reactions, uncertainties, fission fragments, and radiological hazards.
Modified One Group Theory: Media Containing Fuel
Explores the modified one group theory for thermal reactors, focusing on media containing fuel and resonance treatment.
