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NE410/510 - Lecture 2: Neutron Cross Sections

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In this lecture we discuss neutron nuclear cross sections, including their structure, underlying physics, how they are measured, and how they are used in computational simulations.
NE410/510 - Lecture 2: Neutron Cross Sections
NE410/510 - Lecture 3: The Physics of Nuclear Fission
NE410/510 - Lecture 1: Introduction to Nuclear Reactor Theory
NE410/510 - Lecture 4: Elastic Scattering Kinematics
NE410/510 - Lecture 11: The Diffusion Equation for Reflected Geometries
NE410/510 - Lecture 18: Nuclear Reactor Kinetics
NE410/510 - Lecture 10: The Diffusion Equation in Multiple Dimensions
NE410/510 - Lecture 14: Generating Multigroup Cross Sections and Neutron Flux Spectra
NE410/510 - Lecture 8: The P1 Approximation and the Neutron Diffusion Equation
NE410/510 - Lecture 12: Finite Difference Diffusion Methods
NE410/510 - Lecture 9: The Critical Condition and Vacuum Boundary Conditions
NE410/510 - Lecture 13: Multigroup Diffusion Equations
NE410/510 - Lecture 16: Resonance-region Flux Spectra and Resonance Escape Probabilities
NE410/510 - Lecture 15: Lethargy and Introduction to Slowing-Down Theory
Lecture 2 Continuation Neutron flux in slab reactor
NE410/510 - Lecture 5: The Four- and Six-Factor Formulas
NE410/510 - Lecture 6: The Boltzmann Transport Equation
NE499/515 - Lecture 1: Introduction to Nuclear Criticality Safety
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