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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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28 <strong>Monte</strong> <strong>Carlo</strong> <strong>Particle</strong> <strong>Transport</strong> <strong>Methods</strong>: <strong>Neutron</strong> <strong>and</strong> <strong>Photon</strong> CalculationsFIGURE 2.7.A particle night crossing boundaries of zones of different materials.denotes the number of particles entering a collision with coordinates dP about P <strong>and</strong> itsname is incoming density, or simply collision density.From the above definitions it is clear that none of these functions is a "density function"since generally the normalization conditionsJ X(P) dP = 1<strong>and</strong>Ji|/(P)dP = 1are not satisfied.The incoming density is closely related to the flux. Let us recall the definition of theflux (fluence, by the rigorous ICRU terminology):(r,E)dadEis the number of particles entering an infinitesimal sphere of radius dr. cross-sectional areaof da = Tr (dr) 2with direction <strong>and</strong> energy dE about E. The expected path length ofthese particles is (see Equation 2.14)4--- - dpThus the expected number of particles entering collisions in the infinitesimal sphere(i.e. the collision density) isi|i(r,E)dr dE = a(r,E) < d( >

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