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262    APPENDIX C Basic reactor physics




                                 Incident neutron data / ENDF/B-VII.1 / U238 / MT = 102: (z, Y ) / Cross section

                          10000

                           1000
                           100

                           Cross-section (b)  0,1 1  Incident energy (meV)
                            10
                                             g
                                       1/v region
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                                        /
                                        /
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                                        /
                                        /
                                       1/ 1/v region
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                                        d
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                                          nt
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                                            ene
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                                              rg
                                              rg
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                                                 (m
                                                y
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                                                y
                                                   eV)
                                                 m
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                                                   V)
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                                                 m
                                        ide
                                        ide
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                                      Inc
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                                        d
                                        d
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                                        d
                           0,01
                                             n
                                                     rg
                                                        (
                                             n
                                            Inc
                                            Inc ide nt  ene rg y y y  ( (m eV) ) )
                                            Incident energy (meV)
                                                     rg
                                            Incident energyy (meV)
                          0,001
                           1E-4
                             1E-11  1E-10  1E-9  1E-8  1E-7  1E-6  1E-5  1E-4  0,001  0,01  0,1  1  10
                                                     Incident energy (MeV)
                         FIG. C.2
                         U-238 neutron cross section as a function of neutron energy ([5], source ENDF, JANIS 4.0]).
                            Resonances influence the ability of fission neutrons to slow down to thermal
                         energy without capture. Resonance escape probability influences criticality
                         calculations.
                            Resonances also affect reactor dynamics by two mechanisms. The heavy isotopes
                         in the fuel experience Doppler broadening as the fuel temperature increases. Doppler
                         broadening is the reduction of a resonance peak while increasing the energy span of
                         the resonance. See Fig. C.3. Since the cross section is still very large in the broadened
                         energy region, the net effect is an increase in the resonance absorption rate. Neutron
                         capture in fertile materials (U-238 and Th-232) and Pu-240 (produced by captures in
                         U-238 and Pu-239) exceeds fissions due to Doppler broadening in fissile material
                         resonances. Therefore, Doppler broadening causes reactivity to decrease when fuel
                         temperature increases. So, the fuel temperature coefficient of reactivity (reactivity
                         change/fuel temperature change) is always negative. The negative fuel temperature
                         coefficient is very important in ensuring that a reactor responds satisfactorily in a
                         transient.
                            Low energy resonances (principally between 0.1 eV and 1.0 eV) affect the
                         reactivity change following a change in moderator temperature. The thermal energy
                         spectrum hardens (shifts to higher energies). Consequently, higher moderator
                         temperature causes more thermal neutrons to exist at energies where the
                         resonances occur.
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