Page 256 - Dynamics and Control of Nuclear Reactors
P. 256

APPENDIX C Basic reactor physics     257




                                                             3
                  •  N¼Density of target nuclei (number of nuclei/cm )
                                                         3
                                                                1
                                                     2
                  •  Macroscopic cross section: Σ¼σN (cm /cm or cm )
                                                             3
                  •  Reaction rate: R¼Σϕ (number of interactions/cm -s)
                  •  Fission reaction rate: R f ¼Σ f ϕ
                  •  R f ¼[Nσ f ] [n(t)v]
                                                     3
                  •  R f is the number of fission reactions/cm -s
                  •  σ f is the microscopic fission cross section
                  The reaction rate in a 1/v absorber is given by
                                                R ¼ N σϕ
                  or
                                              R ¼ Nc=vÞnv
                                                  ð
                  where c is a constant.
                     Note that the velocity terms cancel. Therefore, the reaction rate for 1/v absorbers
                  is independent of the neutron energy.


                   Example C.1
                    The energy of neutrons in an experimental reactor is approximately equal to 0.0253 eV. This
                    corresponds to a speed of about 2200 m/s for neutrons. As an exercise, let us let flux
                               2
                           12
                    ϕ¼2 10 /(cm s). Calculate the neutron density.
                                                12
                                            2 10 cm  2  s  1
                                                             6
                                     n ¼ ϕ=v ¼          ¼ 9 10 =cm 3
                                            2200 100m s  1
                     In the above example, use the microscopic absorption cross section, σ a ¼694 b
                                                                   3
                                                               24
                  for U-235. The density of target nuclei is N¼0.05 10 /cm . Then
                                            Σ a ¼ Nσ a ¼ 34 cm  1
                  The reaction rate is given by the following:
                                                            3
                                                       13
                                         R ¼ ϕΣ a ¼ 6:8 10 =cm s
                  R is also the rate at which U-235 nuclei are consumed.
                     Note that the microscopic fission cross section of U-235 at E¼0.025 eV is,
                  σ f ¼582 b. The capture cross section is σ c ¼112 b and the absorption cross section
                  is σ a ¼σ f +σ c ¼694. The ratio σ f /σ a ¼582/694¼0.84. That is, 84% of thermal
                  neutron absorptions in U-235 result in a fission reaction.
                     If an absorber cross section decreases slower with increasing neutron energy (and
                  neutron velocity) than 1/v, then the absorption rate relative to 1/v absorbers increases
                  as neutron energy increases. The reverse is true for absorbers whose cross section
                  decreases faster than 1/v. The energy dependence of low energy absorptions plays
                  an important role in determining the dynamics of power reactors.
                     The power produced in a reactor is given by the following:
                                           P ¼ NVÞ σ f nv FWatt                  (C.3)
                                              ð
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