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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
7.
Nuclear Fission Process
7.1.
Neutron-Induced Fission
7.1.1.
Fissionable Isotopes
7.1.1.1.
U-235
7.1.1.2.
Pu-239
7.1.1.3.
U-233
7.1.2.
Fission Mechanism
7.1.2.1.
Neutron Absorption
7.1.2.2.
Compound Nucleus Formation
7.1.2.3.
Nuclear Deformation
7.1.2.4.
Fragment Formation
7.1.3.
Fission Products
7.1.3.1.
Mass Distribution
7.1.3.2.
Neutron Emission
7.1.3.3.
Energy Release
7.2.
Chain Reaction
7.2.1.
Criticality Concepts
7.2.1.1.
Multiplication Factor
7.2.1.2.
Critical Mass
7.2.1.3.
Neutron Balance
7.2.2.
Neutron Physics
7.2.2.1.
Neutron Generation
7.2.2.2.
Neutron Absorption
7.2.2.3.
Neutron Leakage
7.2.3.
Control Methods
7.2.3.1.
Control Rods
7.2.3.2.
Neutron Poisons
7.2.3.3.
Moderator Control
7.3.
Energy Release and Conversion
7.3.1.
Fission Energy Distribution
7.3.1.1.
Kinetic Energy of Fragments
7.3.1.2.
Neutron Energy
7.3.1.3.
Gamma Radiation
7.3.1.4.
Beta Decay Energy
7.3.2.
Heat Generation
7.3.2.1.
Prompt Heat
7.3.2.2.
Decay Heat
7.3.2.3.
Heat Removal Requirements
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6. Fuel Fabrication
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8. Fuel Performance in Reactor