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260    APPENDIX C Basic reactor physics




                          Table C.1 Energy distribution for fission induced by thermal neutrons in
                          U-235.
                          Source                                             Energy (MeV)
                          Fission product KE                                  168
                          Neutron KE                                            5
                          Energy in gamma radiation (instantaneous and delayed)  11
                          Energy in β-decay of fission products                 7
                          • Total (available as thermal energy):              191
                          Energy not available as heat                         11
                          • Total energy created in one fission reaction:     202


                            The neutron binding energies of U-235, U-233, and U-239 nuclei (odd number of
                         neutrons) are about I MeV higher than the nuclei of Th-232 and U-238 (even number
                         of neutrons). This additional binding energy is sufficient to exceed the critical energy
                         for fission, with low-energy neutrons. For example: for U-235, critical energy for
                         fission to occur is 5.5 MeV and the binding energy of an extra neutron is
                         6.6 MeV. The critical and binding energies for U-238 are 5.9 MeV and 4.9 MeV.
                            Out of two to three neutrons released per fission (depending on the fissioning iso-
                         tope involved), one of these is used to produce the next fission reaction in a steady-
                         state chain reaction. The remaining neutrons are consumed by
                         •  Leakage from the core
                         •  Capture by non-fuel reactor constituents (such as coolant, moderator and
                            structural materials)
                         •  Non-fission capture in the fuel (radiative capture)
                         •  Capture by the fertile nuclei (such as U-238, resonance capture).

                         The distribution of fission energy in various forms is shown in Table C.1.



                         C.5 Fast and thermal neutrons
                         Immediately following fission, the neutrons possess high kinetic energy, in the
                         million-eV range (0.1–15 MeV). Most current-generation reactors include a material
                         (called a moderator) whose purpose is to slow down neutrons while capturing few
                         neutrons. Fast neutrons lose their energy due to scattering collisions with various
                         nuclei in the medium (especially in the moderator, see Section C.2), and become
                         slow neutrons (energy <1 eV).
                            It should be noted that tabulated cross sections are usually for monoenergetic neu-
                         trons at an energy of 0.0253 eV or a speed of 2200 m/s. This energy corresponds to a
                         temperature of 20 °C or 293 K. Thermal neutrons are those whose kinetic energy
                         reaches equilibrium with the thermal energy of the moderator. Higher moderator
                         temperature means greater thermal motion of moderator atoms and a consequent
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