Page 260 - Dynamics and Control of Nuclear Reactors
P. 260

APPENDIX C Basic reactor physics     261




                  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. C.1 shows distributions at
                  three different temperatures.
                     In a reactor, the absorption and fission cross sections must be corrected for the
                  actual temperature of the moderator. The Maxwell-Boltzmann distribution applies
                  for neutrons in equilibrium with moderator atoms. As shown in elementary reactor
                  physics books, the “effective” cross section for a material with 1/v dependence in a
                  moderator at temperature, T is

                                                 r ffiffiffiffiffiffiffiffi
                                              1    293
                                                      ð
                                       σ TðÞ ¼       σ 0:0253eVÞ                 (C.9)
                                             1:128  T
                  The average and most probable energies for neutrons in a Maxwell spectrum are as
                  follows:
                  – average neutron energy¼1/2 kT
                  – most probable neutron energy¼3/2 kT.

                  where k is the Boltzmann constant and T is the absolute temperature.
                     Clearly the thermal spectrum shifts to higher energies as moderator temperature
                  increases. This is called spectral hardening.
                     Resonances are spikes in a material’s cross section. See Fig. C.2 for the energy-
                  dependent U-238 cross section. Strong resonances are apparent. Resonances are
                  important in their effects on steady state and dynamic characteristics of a reactor.
                  Capture and fission cross sections both exhibit resonant behavior.



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










                    0 1
                     0    1000  2000  3000  4000  5000   6000  7000  8000  9000  10000
                                            v, Neutron velocity (m/s)
                  FIG. C.1
                  Maxwell-Boltzmann distribution of thermal neutrons for three temperatures.
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