Nuclear Waste Series - 5: Should we launch our waste into space?
Nuclear Engineering Lectures
Nuclear Waste Series - 5: Should we launch our waste into space?
14:06
Nuclear Waste Series - 4: Should we dump our nuclear waste into the ocean!?!
Nuclear Engineering Lectures
Nuclear Waste Series - 4: Should we dump our nuclear waste into the ocean!?!
10:41
Nuclear Waste Series - 3: Reprocessing and Recycling Spent Fuel
Nuclear Engineering Lectures
Nuclear Waste Series - 3: Reprocessing and Recycling Spent Fuel
17:34
Nuclear Waste Series - 2: Yucca Mountain and Geological Repositories
Nuclear Engineering Lectures
Nuclear Waste Series - 2: Yucca Mountain and Geological Repositories
44:40
Nuclear Waste Series - 1: What is Nuclear Waste?
Nuclear Engineering Lectures
Nuclear Waste Series - 1: What is Nuclear Waste?
11:49
NE410/510 - Lecture 19: A Reactor Physics Explanation of the Chernobyl Disaster
Nuclear Engineering Lectures
NE410/510 - Lecture 19: A Reactor Physics Explanation of the Chernobyl Disaster
35:01
NE499/515 - Lecture 21: Nuclear Criticality Safety Evaluations
Nuclear Engineering Lectures
NE499/515 - Lecture 21: Nuclear Criticality Safety Evaluations
12:13
NE499/515 - Lecture 20: The TSURFER Data Assimilation/Data Adjustment Method
Nuclear Engineering Lectures
NE499/515 - Lecture 20: The TSURFER Data Assimilation/Data Adjustment Method
21:08
NE499/515 - Lecture 19: The Whisper Extreme Value Theory Method
Nuclear Engineering Lectures
NE499/515 - Lecture 19: The Whisper Extreme Value Theory Method
11:41
NE499/515 - Lecture 18: Benchmark Similarity Coefficients and the TSUNAMI-IP Code
Nuclear Engineering Lectures
NE499/515 - Lecture 18: Benchmark Similarity Coefficients and the TSUNAMI-IP Code
16:28
NE499/515 - Lecture 17: Sensitivity Analysis in Nuclear Criticality Safety
Nuclear Engineering Lectures
NE499/515 - Lecture 17: Sensitivity Analysis in Nuclear Criticality Safety
28:09
NE499/515 - Lecture 16: Trending Analysis and Upper Subcritical Limits
Nuclear Engineering Lectures
NE499/515 - Lecture 16: Trending Analysis and Upper Subcritical Limits
12:52
NE499/515 - Lecture 15: A Statistics Review for Upper Subcritical Limit Estimates
Nuclear Engineering Lectures
NE499/515 - Lecture 15: A Statistics Review for Upper Subcritical Limit Estimates
13:21
NE499/515 - Lecture 14: Introduction to Code Validation and Upper Subcritical Limits
Nuclear Engineering Lectures
NE499/515 - Lecture 14: Introduction to Code Validation and Upper Subcritical Limits
19:25
NE499/515 - Lecture 13: Nuclear Data and Integral Benchmark Experiments
Nuclear Engineering Lectures
NE499/515 - Lecture 13: Nuclear Data and Integral Benchmark Experiments
17:35
Nuclear Science Week Shorts: The Monte Carlo Method, Using Random Numbers to Design Nuclear Reactors
Nuclear Engineering Lectures
Nuclear Science Week Shorts: The Monte Carlo Method, Using Random Numbers to Design Nuclear Reactors
7:23
Uncertainty Quantification in Nuclear Engineering Applications
Nuclear Engineering Lectures
Uncertainty Quantification in Nuclear Engineering Applications
30:50
NE499/515 - Lecture 12: Postings, Procedures, and the Wood River Junction Accident (CA-9)
Nuclear Engineering Lectures
NE499/515 - Lecture 12: Postings, Procedures, and the Wood River Junction Accident (CA-9)
17:46
NE499/515 - Lecture 11: Interactions with Operations and the LASL 1958 Accident (CA-8)
Nuclear Engineering Lectures
NE499/515 - Lecture 11: Interactions with Operations and the LASL 1958 Accident (CA-8)
15:46
NE499/515 - Lecture 10: Safety Culture and the Boeing 737 MAX Airplane Crashes
Nuclear Engineering Lectures
NE499/515 - Lecture 10: Safety Culture and the Boeing 737 MAX Airplane Crashes
16:14
NE499/515 - Lecture 9: Criticality Accident Alarm Systems and the Y-12 1958 Accident (CA-7)
Nuclear Engineering Lectures
NE499/515 - Lecture 9: Criticality Accident Alarm Systems and the Y-12 1958 Accident (CA-7)
13:27
NE499/515 - Lecture 8: Nuclear Reactor Kinetics and the Tokai-Mura Criticality Accident (CA-6)
Nuclear Engineering Lectures
NE499/515 - Lecture 8: Nuclear Reactor Kinetics and the Tokai-Mura Criticality Accident (CA-6)
23:29
NE499/515 - Lecture 7: Process Analysis and the Tomsk 1978 Criticality Accident (CA-5)
Nuclear Engineering Lectures
NE499/515 - Lecture 7: Process Analysis and the Tomsk 1978 Criticality Accident (CA-5)
20:13
NE499/515 - Lecture 6: The MAGIC MERV Criticality Safety Controls
Nuclear Engineering Lectures
NE499/515 - Lecture 6: The MAGIC MERV Criticality Safety Controls
17:19
NE499/515 - Lecture 5: Limits and Controls and the Mayak 1953 Accident (CA-4)
Nuclear Engineering Lectures
NE499/515 - Lecture 5: Limits and Controls and the Mayak 1953 Accident (CA-4)
19:44
NE499/515 - Lecture 4: ANSI/ANS Standards in Criticality Safety
Nuclear Engineering Lectures
NE499/515 - Lecture 4: ANSI/ANS Standards in Criticality Safety
11:56
NE499/515 - Lecture 3: The Boltzmann Transport Equation and the Mayak 1958 Accident (CA-3)
Nuclear Engineering Lectures
NE499/515 - Lecture 3: The Boltzmann Transport Equation and the Mayak 1958 Accident (CA-3)
19:12
NE499/515 - Lecture 2: Health Effects of Radiation and the "Demon Core" Accidents (CA-1 and CA-2)
Nuclear Engineering Lectures
NE499/515 - Lecture 2: Health Effects of Radiation and the "Demon Core" Accidents (CA-1 and CA-2)
26:58
NE499/515 - Lecture 1: Introduction to Nuclear Criticality Safety
Nuclear Engineering Lectures
NE499/515 - Lecture 1: Introduction to Nuclear Criticality Safety
10:54
NE410/510 - Lecture 18: Nuclear Reactor Kinetics
Nuclear Engineering Lectures
NE410/510 - Lecture 18: Nuclear Reactor Kinetics
9:49
NE410/510 - Lecture 17: Homogenization
Nuclear Engineering Lectures
NE410/510 - Lecture 17: Homogenization
12:21
NE410/510 - Lecture 16: Resonance-region Flux Spectra and Resonance Escape Probabilities
Nuclear Engineering Lectures
NE410/510 - Lecture 16: Resonance-region Flux Spectra and Resonance Escape Probabilities
15:25
NE410/510 - Lecture 15: Lethargy and Introduction to Slowing-Down Theory
Nuclear Engineering Lectures
NE410/510 - Lecture 15: Lethargy and Introduction to Slowing-Down Theory
10:05
NE410/510 - Lecture 14: Generating Multigroup Cross Sections and Neutron Flux Spectra
Nuclear Engineering Lectures
NE410/510 - Lecture 14: Generating Multigroup Cross Sections and Neutron Flux Spectra
15:35
NE410/510 - Lecture 13: Multigroup Diffusion Equations
Nuclear Engineering Lectures
NE410/510 - Lecture 13: Multigroup Diffusion Equations
13:52
NE410/510 - Lecture 12: Finite Difference Diffusion Methods
Nuclear Engineering Lectures
NE410/510 - Lecture 12: Finite Difference Diffusion Methods
13:38
NE410/510 - Lecture 11: The Diffusion Equation for Reflected Geometries
Nuclear Engineering Lectures
NE410/510 - Lecture 11: The Diffusion Equation for Reflected Geometries
9:36
NE410/510 - Lecture 10: The Diffusion Equation in Multiple Dimensions
Nuclear Engineering Lectures
NE410/510 - Lecture 10: The Diffusion Equation in Multiple Dimensions
8:52
NE410/510 - Lecture 9: The Critical Condition and Vacuum Boundary Conditions
Nuclear Engineering Lectures
NE410/510 - Lecture 9: The Critical Condition and Vacuum Boundary Conditions
12:44
NE410/510 - Lecture 8: The P1 Approximation and the Neutron Diffusion Equation
Nuclear Engineering Lectures
NE410/510 - Lecture 8: The P1 Approximation and the Neutron Diffusion Equation
15:18
NE410/510 - Lecture 7: The Moments of the Boltzmann Transport Equation
Nuclear Engineering Lectures
NE410/510 - Lecture 7: The Moments of the Boltzmann Transport Equation
13:05
NE410/510 - Lecture 6: The Boltzmann Transport Equation
Nuclear Engineering Lectures
NE410/510 - Lecture 6: The Boltzmann Transport Equation
11:38
NE410/510 - Lecture 5: The Four- and Six-Factor Formulas
Nuclear Engineering Lectures
NE410/510 - Lecture 5: The Four- and Six-Factor Formulas
8:09
NE410/510 - Lecture 4: Elastic Scattering Kinematics
Nuclear Engineering Lectures
NE410/510 - Lecture 4: Elastic Scattering Kinematics
17:54
NE410/510 - Lecture 3: The Physics of Nuclear Fission
Nuclear Engineering Lectures
NE410/510 - Lecture 3: The Physics of Nuclear Fission
16:53
NE410/510 - Lecture 2: Neutron Cross Sections
Nuclear Engineering Lectures
NE410/510 - Lecture 2: Neutron Cross Sections
16:15
NE410/510 - Lecture 1: Introduction to Nuclear Reactor Theory
Nuclear Engineering Lectures
NE410/510 - Lecture 1: Introduction to Nuclear Reactor Theory
14:48
NE560 - Lecture 20: Dual-Temperature Reactor Feedback
Nuclear Engineering Lectures
NE560 - Lecture 20: Dual-Temperature Reactor Feedback
12:25
NE560 - Lecture 19: Reactor Dynamic Behavior with Moderator Feedback
Nuclear Engineering Lectures
NE560 - Lecture 19: Reactor Dynamic Behavior with Moderator Feedback
11:18
NE560 - Lecture 18 - The Nuclear Reactor Transfer Function
Nuclear Engineering Lectures
NE560 - Lecture 18 - The Nuclear Reactor Transfer Function
11:16
NE560 - Lecture 17: Stability Analysis with Bode Plots – Gain and Phase Margins
Nuclear Engineering Lectures
NE560 - Lecture 17: Stability Analysis with Bode Plots – Gain and Phase Margins
8:53
NE560 - Lecture 16: Bode Plots for Additional s-Domain Polynomials
Nuclear Engineering Lectures
NE560 - Lecture 16: Bode Plots for Additional s-Domain Polynomials
10:32
NE560 - Lecture 15: Introduction to Bode Plots
Nuclear Engineering Lectures
NE560 - Lecture 15: Introduction to Bode Plots
13:34
NE560 - Lecture 14: Root Locus Analysis
Nuclear Engineering Lectures
NE560 - Lecture 14: Root Locus Analysis
12:47
NE560 - Lecture 13: Introduction to Stability Analysis
Nuclear Engineering Lectures
NE560 - Lecture 13: Introduction to Stability Analysis
18:09
NE560 - Lecture 12: Laplace Transform Applications
Nuclear Engineering Lectures
NE560 - Lecture 12: Laplace Transform Applications
11:30
NE560 - Lecture 11: Laplace Transforms
Nuclear Engineering Lectures
NE560 - Lecture 11: Laplace Transforms
12:26
NE560 - Lecture 10: Introduction to Classical Control Theory
Nuclear Engineering Lectures
NE560 - Lecture 10: Introduction to Classical Control Theory
7:58
NE560 - Lecture 9: A Reactor Dynamics Solution for Prompt Supercritical Transients
Nuclear Engineering Lectures
NE560 - Lecture 9: A Reactor Dynamics Solution for Prompt Supercritical Transients
14:22
NE560 - Lecture 8: The Prompt Jump Approximation and Prompt Kinetics Approximation
Nuclear Engineering Lectures
NE560 - Lecture 8: The Prompt Jump Approximation and Prompt Kinetics Approximation
16:19
NE560 - Lecture 7: The Inhour Equation
Nuclear Engineering Lectures
NE560 - Lecture 7: The Inhour Equation
6:41
NE560 - Lecture 6: Approximations to the Point Kinetics Equations
Nuclear Engineering Lectures
NE560 - Lecture 6: Approximations to the Point Kinetics Equations
11:54
NE560 - Lecture 5: The Exact Point Reactor Kinetics Equations
Nuclear Engineering Lectures
NE560 - Lecture 5: The Exact Point Reactor Kinetics Equations
16:14
NE560 - Lecture 4: The Perturbation Equations
Nuclear Engineering Lectures
NE560 - Lecture 4: The Perturbation Equations
13:09
NE560 - Lecture 3: The Adjoint Boltzmann Transport Equation
Nuclear Engineering Lectures
NE560 - Lecture 3: The Adjoint Boltzmann Transport Equation
11:01
NE560 - Lecture 2: The Adjoint Flux and Operator Notation
Nuclear Engineering Lectures
NE560 - Lecture 2: The Adjoint Flux and Operator Notation
13:30
NE560 - Lecture 1: Intro to Kinetics and Dynamics
Nuclear Engineering Lectures
NE560 - Lecture 1: Intro to Kinetics and Dynamics
17:37