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Monte Carlo Particle Transport Methods: Neutron and Photon - gnssn

Monte Carlo Particle Transport Methods: Neutron and Photon - gnssn

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365neutron density, S 0 for every r such thatdrZ.ir.rd > 0i.e., V is definitely positive at every point that can serve as a starting point of fission neutronscontributing to the generation of next-generation fission neutrons. LetSrXr) = S(r)V(r)<strong>and</strong>Zir.r'l = V(r)Z(r,r')/V(r') (6.129)Then Equation (6.126) can be rewritten asSr(r) = jdr'Z(r,r')£f(r') (6.130)Equation (6.130) is analogous to Equation (6.126) <strong>and</strong> defines an iterative procedure similarto that in Equation (6.127):cf (n) (r) = jdr'Z(r,r')y ( n -"(r') (6.131)By analogy to Equation (6.128), an estimate of k eiTfrom the n-th <strong>and</strong> (n — l)-th generationsreadsk„ = Jdr^ryJdrcT^ ')(r') (6.132)Now, if the importance function V(f) is the solution of the equationV(r) = — jdr'V(r')Z(r',r) (6.133)

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