Course curriculum

  • 1

    Chapter 1 - Let's get started!

  • 2

    Chapter 2 - Mechanical- Thermal-Hydraulic- and Nuclear Design

    • Mechanical Design – 10 h

    • Mechanical Design Review - Presentation for upcoming lecture

    • Mechanical Design Review

    • Thermal-Hydraulic Design – 1 h

      FREE PREVIEW

    • Thermal-Hydraulic Design - Presentation for upcoming lecture

    • Thermal-Hydraulic Design

    • Thermal-Hydaulic Fuel Design Audit PWRs & BWRs – 2 h

    • Nuclear Design Audit - Presentation for upcoming lecture

    • Nuclear Design Audit

    • First two chapters completed! What did you think?
  • 3

    Chapter 3 - Fabrication and Manufacturing

    • Introduction and Pellet Fabrication – 2 h

    • Zirconium Alloy Component Fabrication – 1 h

    • Pellet Production

    • Zirconium Alloy Manufacturing – 5 h

    • Zirconium Alloy Manufacturing
  • 4

    Chapter 4 - Fuel rods and Spacers

    • Fuel Rod

    • Grid-Spacer Manufacturing – 1 h

    • Spacers
  • 5

    Chapter 5 - End fittings, assembly and more!

    • End Fitting Manufacturing – 1 h

    • End Fittings

    • Fuel Assembly Manufacturing – 1 h

    • Channel Manufacturing – 3 h

    • Bundle Assembly

    • BWR Fuel Outer Channels

    • Dimensional Stability
  • 6

    Test - Fuel Design and Manufacturing

    • Test - Fuel Design and Manufacturing
  • 7

    Chapter 6 - Zirconium and basic Metallurgy

    • Zirconium Alloy Materials – 2 h

    • Microstructure and Effect of Irradiation on Zirconium –3 h

    • Basic Metallurgy and Microstructure
  • 8

    Chapter 7 - Fuel Reliability

    • Fuel Reliability, Primary Failures and Secondary Degradation – 4 h

    • Fuel Reliability (1 of 2)

    • Fuel Reliability (2 of 2)
  • 9

    Chapter 8 - Corrosion and HPU

    • Corrosion and HPU – 13 h

    • Corrosion and HPU
  • 10

    Chapter 9 - Dimensional Stability

    • Dimensional Stability, Introduction – 1 h

    • Dimensional Stability Introduction in LWRs
  • 11

    Chapter 10 - Irradiation Creep & Irradiation Growth

    • Irradiation Creep –3 h

    • Irradiation Creep

    • Irradiation Growth – 3 h

    • Irradiation Growth
  • 12

    Chapter 11 - Fuel Channel Bowing

    • Fuel Channel Bowing – 8 h

    • Bow of BWR Channels
  • 13

    Test - Fuel Performance during normal operation - Part 1 of 2

    • Fuel Performance during normal operation Part 1 of 2
  • 14

    Chapter 12 - Deformation and Mechanical properties

    • Deformation and Mechanical Properties of Zirconium Alloys– 3 h

    • Deformation and Mechanical Properties of Zirconium Alloys
  • 15

    Chapter 13 - Hydrogen

    • The Effect of Hydrogen on Zirconium Alloy Properties - 11 h

    • Hydrogen and Hydrides
  • 16

    Chapter 14 - PCI

    • Pellet Cladding Interaction - PCI – 3 h

    • Pellet Cladding Interaction - PCI
  • 17

    Chapter 15 - UO2 and MOX

    • UO2 and MOX Fuel – 2 h

    • UO2 and MOX Fuel (1 of 4)

    • UO2 and MOX Fuel (2 of 4)

    • UO2 and MOX Fuel (3 of 4)

    • UO2 and MOX Fuel (4 of 4)
  • 18

    Chapter 16 - Performance

    • Performance of Stainless Steel and Nickel Base Alloys – 3 h

    • Fuel Performance Codes – 2 h

    • Performance of Ni-base Alloys
  • 19

    Test - Fuel Performance during normal operation - Part 2/2

    • Fuel Performance During Normal Operation and Anticipated Operational Occurrences Part 2/2
  • 20

    Chapter 17 - LOCA & RIA

  • 21

    Final Exam

    • Final Exam - BWR Nuclear Fuel Engineering

    • What did you think of this course?