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Engineering
Nuclear Engineering
Nuclear Fuel Cycle
1. Introduction to the Nuclear Fuel Cycle
2. Uranium Exploration and Mining
3. Milling and Concentration
4. Uranium Conversion
5. Uranium Enrichment
6. Fuel Fabrication
7. Nuclear Fission Process
8. Fuel Performance in Reactor
9. Fuel Handling and Refueling
10. Spent Nuclear Fuel Characteristics
11. Interim Storage of Spent Fuel
12. Transportation of Nuclear Materials
13. Reprocessing of Spent Fuel
14. Mixed Oxide Fuel
15. Radioactive Waste Classification
16. Waste Treatment and Conditioning
17. Long-Term Disposal
18. Thorium Fuel Cycle
19. Fast Reactor Fuel Cycles
20. Partitioning and Transmutation
21. IAEA Safeguards System
22. Nuclear Material Accountancy
23. Physical Protection
24. Economic Analysis of Fuel Cycles
25. Environmental Impact Assessment
26. Sustainability and Resource Management
10.
Spent Nuclear Fuel Characteristics
10.1.
Composition of Spent Fuel
10.1.1.
Residual Uranium
10.1.1.1.
U-235 Content
10.1.1.2.
U-238 Content
10.1.2.
Plutonium Content
10.1.2.1.
Pu-239
10.1.2.2.
Pu-240
10.1.2.3.
Pu-241
10.1.2.4.
Other Isotopes
10.1.3.
Minor Actinides
10.1.3.1.
Neptunium
10.1.3.2.
Americium
10.1.3.3.
Curium
10.1.4.
Fission Products
10.1.4.1.
Short-Lived Isotopes
10.1.4.2.
Long-Lived Isotopes
10.1.4.3.
Stable Isotopes
10.2.
Radioactivity and Heat Generation
10.2.1.
Decay Heat
10.2.1.1.
Time Dependence
10.2.1.2.
Cooling Requirements
10.2.2.
Radiation Fields
10.2.2.1.
Gamma Radiation
10.2.2.2.
Neutron Emission
10.2.2.3.
Alpha Radiation
10.2.2.4.
Beta Radiation
10.2.3.
Shielding Requirements
10.2.3.1.
Material Selection
10.2.3.2.
Thickness Calculations
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9. Fuel Handling and Refueling
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11. Interim Storage of Spent Fuel