Neutron Detection in Nuclear Reactors: MiMi Detectors

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Introduction to Nuclear Engineering: Reactor Kinetics

Introduces reactor kinetics in nuclear engineering, covering reactivity control, critical conditions, moderator materials, and chain reaction control.

Neutron Physics: Reactor Fundamentals

Explores neutron physics in nuclear reactors, covering criticality, fuel cycles, reactor characteristics, and slowing down processes.

Interactions of Neutrons with Matter

Explores the interaction of neutrons with matter through cross sections, scattering, absorption, and energy dependencies.

Nuclear Reactors: Multigroup Theory

Covers the basics of nuclear reactors, including nuclear fission, neutron diffusion, and multigroup theory.

Modified One Group Theory: Media Containing Fuel

Explores the modified one group theory for thermal reactors, focusing on media containing fuel and resonance treatment.

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 Fission Fragments

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

Neutronics Effects of Burnup

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

Neutron moderation

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

Introduction to Nuclear Engineering

Introduces nuclear engineering, covering reactor types, components, and thermodynamics, including pressurized water reactors and boiling water reactors.