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Monte Carlo Particle Transport Methods: Neutron and Photon - gnssn

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126 <strong>Monte</strong> <strong>Carlo</strong> <strong>Particle</strong> <strong>Transport</strong> <strong>Methods</strong>: <strong>Neutron</strong> <strong>and</strong> <strong>Photon</strong> Calculationsvector is very fast. Here, the a ymatrix elements can be computed in a one generation <strong>Monte</strong><strong>Carlo</strong> calculation.Let us now investigate the case where a small perturbation changes the fission neutroncollision density to \*, the fission kernel to K*(P',P) <strong>and</strong> the effective multiplication factorto k* -k* =dPdP'xT(P')K*(P',P)dPxT(P)If the differences are small we may approximate xt asXt(P) = X 1(P) + SXr(P)<strong>and</strong>JdP Xt(P) JdPxXP)1dP8 Xf(P)dP Xf(P)By these approximation the difference between the two multiplication factors is:8k eff= k! ff- k rff= j -1• F JJdPdP' Xl(P)[K*(P',P) -K 1(P',P)]JdPXf(P)ff / d P 8 X f ( P ) ff ]4 j JdPdP'8 Xf(P)K f(P',P) ~ - J JdPdP'[ X f(P) + 8 Xf(P)JK f(P',P) (4.97)JdPx 1(P)If the second <strong>and</strong> third terms of Equation (4.97) may be neglected (§x < x) then theequation reduced toJJdPdP' Xf(P',P) K f(P',P)8k ef= j (4.98)J dP Xf(P)where K.tP'.P) = Kt(P',P) - K(P',P).In this approximation 8k can be obtained in parallel with k cfeffin a correlated <strong>Monte</strong><strong>Carlo</strong>, since only the transport kernels of Equation (4.96) <strong>and</strong> (4.98) differ from each other.<strong>Methods</strong> to evaluate Equation (4.97) with all terms are reviewed by Bernnat.'Criticality is discussed in detail in Chapter 6.III.VIL ADJOINT MONTE CARLOInvestigation of the adjoint transport equations plays an important role in modern <strong>Monte</strong><strong>Carlo</strong> research. Equations adjoint to the transport (collision density) equations can be intra-

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