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7.3 Moderator temperature feedback in thermal reactors     75




                       × 10 –4
                     4
                                                                              293 K
                                                                              493 K
                                                                              593 K
                   Fractional neutron density  2 1
                     3










                     0
                      0    1000  2000  3000  4000  5000  6000  7000  8000  9000  10000
                                            v, Neutron velocity (m/s)
                  FIG. 7.2
                  Maxwell-Boltzmann distribution of thermal neutrons for three temperatures.

                  moderator. Such a change follows a change in heat removal in the secondary system.
                  The moderator temperature coefficient may be positive or negative and its value can
                  change significantly with reactor operation.
                     An increase in the moderator temperature of a thermal reactor causes the thermal
                  energy spectrum of thermalized neutrons to shift to a higher energy. Thermal neu-
                  trons are in equilibrium with the thermal energy of the moderator. Higher moderator
                  temperature means greater thermal motion of moderator atoms and a consequent
                  higher energy of neutrons that interact with the moderator atoms. The energy spec-
                  trum of moderator atoms, and consequently the energy spectrum of thermalized neu-
                  trons is given by the Maxwell-Boltzmann distribution. Fig. 7.2 shows distributions
                  for three different temperatures.
                     Many reactor constituents have absorption and fission cross sections that vary as
                  the reciprocal of neutron velocity. This is called a “1/v” dependence of the cross
                  section, σ. The reaction rate is given by
                                                R ¼ N σφ                         (7.1)
                  or
                                               R ¼ Nσ n v                        (7.2)
                  where
                                                          3
                     R ¼ reaction rate (number of interactions/(cm s)
                                                               3
                     N ¼ absorber number density (number of nuclei/cm )
                                                 2
                     σ ¼ microscopic cross section (cm )
                                                         3
                     n ¼ neutron density (number of neutrons/cm )
                     v ¼ neutron velocity (cm/s)
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