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3.3 Development of the point reactor kinetics equations   21




                  fraction of naturally-occurring Deuterium. Deuterium is also produced in LWRs by
                  neutron absorption in Hydrogen. Consequently, they have a similar, but smaller
                  photoneutron effect than CANDU reactors [1].
                     Molten salt reactors have three components (Li, Be, and C) that are susceptible to
                  photoneutron production with fission gamma rays.



                  3.3 Development of the point reactor kinetics equations
                  The purpose here is to arrive at reactor kinetics equations using the simplest and most
                  intuitive approach. We want to develop a set of ordinary differential equations
                  describing the time evolution of neutron density or reactor power. Many develop-
                  ments have been published that derive the equations from first principles of reactor
                  physics. But all approaches give the same final results and all have the details swept
                  into simple quantities such as k eff and reactivity. Simulations involve the use of
                  specified values of k eff or reactivity as input disturbances or as feedback terms in
                  power reactor simulations where k eff or reactivity feedback is proportional to various
                  process variables such as temperature or pressure.
                     The basic idea in formulating dynamic equations is as follows:
                                                 ð
                                                                 ð
                      ð Rate of change of some quantityÞ ¼ Rate of productionÞ  Rate of lossesÞ  (3.1)
                  For the point kinetics model, the equations are presented below.
                                           dn
                                             ¼ F p P Τ + P d  L a + L            (3.2)
                                           dt

                                       dC i
                                          ¼ F d P Τ  L decay i ¼ 1,2,…,6         (3.3)
                                        dt
                  where

                     n¼neutron density (neutrons per unit volume)
                     F p ¼fraction of neutrons that are released promptly
                     P T ¼total rate of neutron production by fission
                     P d ¼rate of release of delayed neutrons
                     L a+L ¼rate of neutron losses by absorption and leakage
                     F d ¼fraction of neutrons that are released after a delay
                     C i ¼concentration of ith delayed neutron precursor
                     L decay ¼rate of decay of delayed neutron precursors (equal to P d )

                  Let β be defined as the total fraction of neutron production that is delayed and β i be
                  the fraction of fissions that result in production of delayed neutron precursor, C i . The
                  loss of precursor, C i , is given by λ i C i , where λ i is the radioactive decay constant, and
                  is the contribution of the ith precursor to the delayed production term, P d . Since there
                  are multiple precursor species, typically represented by six groups, the equations
                  become
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