Page 264 - Dynamics and Control of Nuclear Reactors
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APPENDIX C Basic reactor physics     265




                     Define the multiplication factor (gain)

                              Number of neutrons generated in the present generation n p
                           k ¼                                                  (C.13)
                              Number of neutrons generated in the previous generation nðÞ
                  If k¼1, the chain reaction is sustained, and the reactor is said to be critical. If k<1,
                  the number of neutrons from one generation to the next decreases. Such a reactor is
                  said to be sub-critical. If k>1, the number of neutrons from one generation to the
                  next increases without bound, and such a reactor is said to be super-critical.
                  In summary:
                  •  k¼1, critical reactor
                  •  k<1, sub-critical reactor
                  •  k>1, super-critical reactor



                  C.9 Computing effective multiplication factor
                  The following factors determine the magnitude of the multiplication factor k:

                  1. Thermal fission factor, η: The factor, η, is defined as the number of fast neutrons
                     produced per thermal neutron absorption in the fuel. That is:
                                                    σ fuel
                                                η ¼ ν  f
                                                     fuel
                                                    σ a
                  2. ν ¼ number of neutrons produced per fission.
                  A typical value for η is around 1.65 for a U-235-fueled thermal reactor.

                  3. Thermal utilization factor, f: The factor, f, is defined as the number of neutron
                     absorptions in the fuel per total number of neutron absorptions. That is:
                                                   Σ fuel
                                                f ¼  a
                                                   Σ total
                                                    a
                  A typical value for f is around 0.71 for a U-235-fueled thermal reactor.
                  4. Resonance escape probability, p: The factor, p, is equal to the number of
                     neutrons that reach thermal energy per fast neutron born. It accounts for
                     neutron losses in resonances during slowing down. A typical value for p is around
                     0.87 for a U-235-fueled thermal reactor.
                  5. Fast fission factor, ε: This factor is defined as the total number of neutrons from
                     both thermal and fast fissions per number of neutrons from thermal fissions.
                     A typical value for ε is around 1.02 for a U-235-fueled thermal reactor

                  Using the above four factors we define the effective multiplication of an infinite
                  size core as
                                               k ∞ ¼ ηfp ε                      (C.14)
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