Lecture 1: Radiation History to the Present
Lecture 2: Radiation-Utilizing Technology
Lecture 3-1: Gemstone Identification, Medical Radiation Technology
Lecture 3-2: Space and Other Radiation Technology
Lecture 4-1: Nuclear Physics for Babies, BNCT
Lecture 4-2: Mass-Energy Equivalence
Lecture 4-3: Don’t Round, Excess Mass, Binding Energy
Lecture 5-1: Mass-Energy Equivalence, No Rounding!
Lecture 5-2: Radioactive Decay Diagrams, Alpha Decay and Energetics
Lecture 5-3: Beta and Positron Decay and Energetics, Neutrinos and Anti-Neutrinos
Lecture 6-1: Electron and Photon Modes of Decay, X-Ray Energies
Lecture 6-2: Auger Electrons, Primordial Nuclides, Mass-Energy Questions
Lecture 6-3: Superheavy Elements and Islands of Stability
Lecture 7-1: Semi-Empirical Mass Formula Physical Terms
Lecture 7-2: Mass-Stability Trends
Lecture 7-3: Semi-Empirical Mass Parabolas of Stability
Lecture 7-4: Stealing Nuclear Data for the Problem Sets with WebPlotDigitizer
Problem set 1 due
Lecture 8-1: Finding the Most Stable Nucleus
Lecture 8-2: Radioactivity, Half Life, Decay Constants
Lecture 8-3: Quantifying Radioactivity from a Real-Life Banana Gamma Spectrum
Lecture 8-4: Identifying Unknown Gamma Rays in a Spectrum
Lecture 9-1: Radioactive Dating Concepts
Lecture 9-2: Radioactive Dating Detection and Accuracy
Lecture 9-3: Specific Activity, Don’t Worry about Fukushima!
Problem set 2 due
Lecture 10-1: Two-Body Kinematics Derivation I
Lecture 10-2: Two-Body Kinematics Derivation II
Lecture 10-3: Two-Body Kinematics Example: Neutron Elastic Scattering
Lecture 11-1: Series Radioactive Decay: Equation Setup
Lecture 11-2: Series Radioactive Decay: Graphing Solutions I
Lecture 11-3: Series Radioactive Decay: Graphing Solutions II
Lecture 11-4: Series Radioactive Decay: Reactor Isotope Production
Lecture 12-1: RTG Power the Easy (Physics) Way
Lecture 12-2: Solving Series Decay without Assumptions
Lecture 12-3: Isotope Production in a Reactor
Problem set 3 due
Lecture 13-1: Tour of Nuclear Reactions and Cross Sections I
Lecture 13-2: Cross Sections II, How the ARC Fusion Reactor Makes Tritium
Lecture 14-1-1: What’s Inside a Cross Section?
Lecture 14-1-2: Linking Cross Sections and Series Radioactive Decay
Lecture 14-1-3: What’s an Absorption Cross Section?
Lecture 14-2: How Many Positrons Do You Emit Per Second?
Lecture 14-3: Making Money with Cobalt-60
Lecture 15-1: Introduction to Photon Interactions
Lecture 15-2: Gamma Spectrum Identification from Photon Interactions
Lecture 15-3: Wasabi Peas Gamma Spectrum Identification
Lecture 15-4: How Photon Detectors Work, Quiz 1 Tips and Logistics
Problem set 4 due
Lecture 16-1: Photon Attenuation
Lecture 16-2: Quantitative Photon Attenuation Curves
Lecture 16-3: Interpreting DEXA Scans, Smuggling Diamonds with 22.01
Quiz 1
Lecture 17-1: Compton Scattering Energetics
Lecture 17-2: Klein-Nishina Angular Differential Cross Section
Lecture 17-3: Photon Attenuation Calculation for Shielding
Lecture 17-4: Toenail Spectrum Identification and Quantification
Lecture 18-1: Photon Weirdness I: Photofission, Designing a Compton Camera
Lecture 18-2: Photon Weirdness II: Inverse Compton Scattering, Gamma Heating
Lecture 19-1: Electronic Stopping Power Derivation I: Setup
Lecture 19-2: Electronic Stopping Power Derivation II: Single Particle Energy Transfer
Lecture 19-3: Electronic Stopping Power Derivation III: Multiple Interactions, Checking Assumptions
Problem set 5 due
Lecture 20-1: Stopping Power Derivation Recap
Lecture 20-2: Limits of Stopping Power Formula Validity, Simplifying It
Lecture 20-3: Online Stopping Power Tables, Graphing Stopping Power
Lecture 20-4: Ultra-Fast Nuclear Stopping Power Derivation from Electronic
Lecture 21-1: Radiative Stopping Power and Bremsstrahlung
Lecture 21-2: Absolute Insanity: Modifying Half Lives!
Lecture 21-3: Bremsstrahlung Energy Spectrum, How an SEM Works
Lecture 21-4: EDX Spectra with Real Bremsstrahlung Background
Lecture 22-1: Neutron Transport Equation: Definitions and First Terms
Lecture 22-2: Neutron Transport Equation: Source and Scattering Terms
Lecture 22-3: Neutron Transport Equation: Copy/Paste to Create Other Neutron Sources/Sinks
Lecture 22-4: Neutron Transport Equation: Cancel ALL the Things!
Lecture 23-1: The Neutron Diffusion Simplification: Treat Neutron Fluxes Like Ideal Gas Atoms!
Lecture 23-2: Solving the Diffusion Equation, and the Concept of Extrapolation Length
Lecture 23-3: Reactor Buckling: Linking Reactor Materials and Geometry to Criticality
Problem set 6 due
Lecture 24-1: Reactor Criticality Relations, Calculating Geometric Buckling
Lecture 24-2: Calculating Real Cross Sections with Flux Averaging from JANIS
Lecture 24-3: Two-Energy Group Neutron Diffusion Theory: The AP-1000 Reactor’s Physical Basis
Lecture 25-1: Radiation Damage Cascades
Lecture 25-2: The Kinchin-Pease Model of Radiation Damage
Lecture 25-3: Relaxing Assumptions in the Kinchin-Pease Model
Lecture 25-4: The Displacement Damage Cross Section
Problem set 7 due
Lecture 26-1: Introduction to Crystal Structure
Lecture 26-2: Point Defects in Crystalline Solids
Lecture 26-3: Larger Defects in Crystalline Solids
Lecture 27-1: Defect Mobility, Radiation Hardening and Embrittlement
Lecture 27-2: Void Swelling, Radiation Induced Segregation
Lecture 27-3: Even More Nuclear Materials Challenges
Quiz 2
Lecture 28-1: Radiation Dose Units, Dose Quality Factors
Lecture 28-2: Tissue Quality Factors for Radiation Dose
Problem set 8 due
Quiz 3
