NE410/510 - Lecture 1: Introduction to Nuclear Reactor Theory

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NE410/510 - Lecture 5: The Four- and Six-Factor Formulas

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NE410/510 - Lecture 3: The Physics of Nuclear Fission

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NE410/510 - Lecture 18: Nuclear Reactor Kinetics

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NE410/510 - Lecture 19: A Reactor Physics Explanation of the Chernobyl Disaster

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NE410/510 - Lecture 8: The P1 Approximation and the Neutron Diffusion Equation

(15:18)

NE410/510 - Lecture 9: The Critical Condition and Vacuum Boundary Conditions

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NE410/510 - Lecture 2: Neutron Cross Sections

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Submarine Nuclear Power | Engineering behind it Nuclear Reactor How it Works

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16. Nuclear Reactor Construction and Operation

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Nuclear Fission

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India vs Australia 5th ODI 2009 at Hyderabad

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MEEN 3398, 2-D 1-Group Neutron Diffusion Equation Solved by MATLAB PDE Toolbox

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410 - Mashup | Sidhu Moose Wala X Shubh | 410 X Bandana | DJ Tanayan | Latest Punjabi Mashups 2024

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23. Solving the Neutron Diffusion Equation, and Criticality Relations

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Near-equilibrium Transport Lecture 7: Boltzmann Transport Equation

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Why Chernobyl Exploded - The Real Physics Behind The Reactor

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3. Nuclear Mass and Stability, Nuclear Reactions and Notation, Introduction to Cross Section

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NE410/510 - Lecture 15: Lethargy and Introduction to Slowing-Down Theory

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NE410/510 - Lecture 17: Homogenization

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NE410/510 - Lecture 13: Multigroup Diffusion Equations

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NE410/510 - Lecture 11: The Diffusion Equation for Reflected Geometries

(9:36)

NE410/510 - Lecture 6: The Boltzmann Transport Equation

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NE410/510 - Lecture 14: Generating Multigroup Cross Sections and Neutron Flux Spectra

(15:35)

NE410/510 - Lecture 10: The Diffusion Equation in Multiple Dimensions

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NE410/510 - Lecture 4: Elastic Scattering Kinematics

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NE410/510 - Lecture 7: The Moments of the Boltzmann Transport Equation

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NE410/510 - Lecture 16: Resonance-region Flux Spectra and Resonance Escape Probabilities

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