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60     CHAPTER 6 Fission product poisoning




                           10 8
                           Ratio of lodine to Xenon  6 4








                            0 2
                            10 12                          10 13                         10 14
                                                                –2
                                                     Neutron flux (#/ cm  s)
                         FIG. 6.1
                         Ratio of steady-state I-135 to Xe-135.




                         6.2.5 Xe-135 poisoning
                         Fission products increase non-fission absorptions. The six-factor formula of reactor
                         physics permits evaluation of the reactivity loss due to increased non-fission absorp-
                         tions. The six-factor formula is:

                                                     k eff ¼ ηε pf L f L s              (6.11)
                         where

                            η¼neutrons produced per absorption in fuel
                            ε¼fast fission factor
                            p¼resonance escape probability
                            f¼thermal utilization factor
                            L f ¼fast neutron non-leakage probability
                            L s ¼thermal neutron non-leakage probability

                         The thermal utilization (f), is the term affected by an increase in fission product quan-
                         tities as follows:

                                                           Σ af
                                                      f ¼                               (6.12)
                                                         Σ af + Σ aO
                         where

                            Σ af ¼macroscopic cross section for absorptions in fissile material
                            Σ aO ¼macroscopic cross section for absorptions in all non-fissile material

                         The presence of fission products alters the thermal utilization as follows:
                                                           Σ af
                                                     0
                                                    f ¼                                 (6.13)
                                                       Σ af + Σ aO + Σ ap
                         where Σ ap ¼macroscopic cross section for absorptions in fission products.
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