Monte Carlo Particle Transport Methods: Neutron and Photon - gnssn

43 sOn the other hand, multiplying Equation (A.3) by Sir.,) and integrating with respect to swe obtain an equation on the function 1 IdP) defined in Equation (.44) as4»(P) = ) dP"u>(P")K s(P",P) 4- jdP'Q(P')T(P',P) (AWhereQ(P) - X(P)S(F)Equation (A. 1) defines 43(P) as the collision density in the i . . u'r-i 1 >the source Q(P). Therefore, Equation (A.5) can be interpr i d .•, i >r,x r irate produced by this collision density. Accordingly, an tirthe reaction rate R in Equation (A.5) goes along the lines det;are started from Q(P). They are processed until they escape fioi.i r n^ •, r i m i >(recall that fission is also treated as absorption). In the simple, .nu, •n >, ,collision contributes to the estimate of R by c,(P)y(P)f(r) mu'o^L U 1 . t! > .of the particle entering the collision. Alternatively, fissiomrel,