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6.2 Dynamics of xenon-135       61




                     Therefore

                                              k eff  1  f  f
                                                      0
                                                   ¼                            (6.14)
                                               k eff  f  0
                  Define the following:
                                                  X
                                                     aO
                                                z ¼ X
                                                     af

                                                   X
                                                     ap
                                                P ¼ X
                                                     af
                  Therefore
                                                k eff  1   P
                                             ρ ¼     ¼                          (6.15)
                                                 k eff  1+ z
                  where ρ¼reactivity decrease due to fission product absorptions.
                     Since z « 1 in a reactor, a rough approximation (good enough to illustrate the
                  approximate magnitude of fission product poisons on reactivity) is.
                                                      Σ ap
                                              ρ ¼ P ¼                           (6.16)
                                                      Σ af
                  Note that the reactivity loss is given by

                                                    σ
                                                    0 aX
                                                ρ ¼ X                           (6.17)
                                                    σ af
                               0
                       0
                  and X (recall X ¼X/N f ) is the solution variable in Eq. (6.6). The ratio of X-135
                                                                             6
                  absorption cross section to U-235 absorption cross section is (3.5 10 )/650 or
                  5380. Therefore
                                                       0
                                              ρ ¼ 5380 XðÞ                      (6.18)
                  At steady state, the Xenon value is given by
                                                    ð γ + γ Þσ f Φ
                                           0         X  I
                                          X ¼ 5380                              (6.19)
                                           ss
                                                    ð λ X + σ aX ΦÞ
                  Using the cross sections for a moderator temperature of 300°C(σ f ¼348 barns
                              6
                  σ aX ¼2.22 10 barns) gives
                                               ð 0:066Þ 348 10  24 Φ
                                    0
                                    ss                5         18
                                   X ¼ 5380                                     (6.20)
                                              2:09 10  +2:22 10  Φ
                  Fig. 6.2 shows the Xe-135 steady state poisoning as a function of neutron flux. Note
                  that the maximum steady state reactivity loss is around eight dollars at high flux
                  levels for this example.
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