Lectures related to Fast-neutron reactor

Introduction to Nuclear Engineering: Gen IV Reactors

Introduces Generation IV nuclear reactors, focusing on fast-spectrum reactors and their sustainability, breeding of fissile fuel, properties of coolants, historical development, advantages, disadvantages, and key challenges.

Reactor Technology: Reactivity Variations and Control

Explores reactivity variations in reactor technology, covering short-term, medium-term, and long-term effects, means of control, and consequences.

Neutron Physics: Reactor Behavior

Covers neutron physics in nuclear reactors, including criticality, fission, and neutron distribution.

Multiplying media: Analytical Solutions and Non-leakage Probability

Covers media containing fuel, analytical solutions, and non-leakage probability for thermal and fast neutrons.

Introduction to Nuclear Engineering: Reactor Kinetics

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

Modified One Group Theory: Media Containing Fuel

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

Neutron Physics: Reactor Fundamentals

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

Introduction to Nuclear Engineering: Chain Reactions and Fuel Cycles

Explores chain reactions, criticality, reactor types, and fuel cycles in nuclear engineering.

Introduction to Nuclear Engineering: Wrap-up

Covers a wide range of topics in nuclear engineering, including reactor technology, safety challenges, and Generation IV concepts.

Neutron Physics: Reactor Overview

Covers neutron interactions, fission products, energy release, and reactor design considerations.

Physics of Nuclear Reactors: Fundamentals and Advanced Concepts

Explores the fundamentals and challenges of nuclear reactors, covering neutron diffusion, fission, breeding, transmutation, and advanced technologies.

Neutron Diffusion Equation: Numerical Methods

Covers numerical methods for solving the neutron diffusion equation and addressing heterogeneous effects in thermal reactors.

Nuclear Reactor Physics

Covers exercises on nuclear reactor physics, including mass calculations, heat evacuation, radioactive equilibrium, and critical parameters.

Neutron Moderation with Absorption

Covers neutron moderation with absorption, including treatment of resonances, temperature effect, and neutron spectra.

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.

Reactor Kinetics: Neutron Behavior and Lattice Effects

Explores neutron behavior in reactors, emphasizing heterogeneous lattices and group constant determination.

Neutron moderation

Covers neutron slowing down, elastic collisions, energy loss, equations, lethargy, and Fermi age theory.

Neutron Moderation

Explores slowing down equations, lethargy, and Fermi age theory in neutron moderation.

Nuclear fission: Energy Release and Fission Fragments

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

Multigroup theory: Two-group method and group structures

Explains the two-group method, group structures, and multi-group constants.