Nuclear Fuel Cycle

  1. Nuclear Fission Process
    1. Neutron-Induced Fission
      1. Fissionable Isotopes
        1. U-235
          1. Pu-239
            1. U-233
            2. Fission Mechanism
              1. Neutron Absorption
                1. Compound Nucleus Formation
                  1. Nuclear Deformation
                    1. Fragment Formation
                    2. Fission Products
                      1. Mass Distribution
                        1. Neutron Emission
                          1. Energy Release
                        2. Chain Reaction
                          1. Criticality Concepts
                            1. Multiplication Factor
                              1. Critical Mass
                                1. Neutron Balance
                                2. Neutron Physics
                                  1. Neutron Generation
                                    1. Neutron Absorption
                                      1. Neutron Leakage
                                      2. Control Methods
                                        1. Control Rods
                                          1. Neutron Poisons
                                            1. Moderator Control
                                          2. Energy Release and Conversion
                                            1. Fission Energy Distribution
                                              1. Kinetic Energy of Fragments
                                                1. Neutron Energy
                                                  1. Gamma Radiation
                                                    1. Beta Decay Energy
                                                    2. Heat Generation
                                                      1. Prompt Heat
                                                        1. Decay Heat
                                                          1. Heat Removal Requirements

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                                                      6. Fuel Fabrication

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                                                      8. Fuel Performance in Reactor