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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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3492. Let i|/ n (P) denote the solution of Equation (6.86) with ¢,,'(?) in place of the firstcollision density3. Insert this solution into Equation (6.87) to define the first iterate of the source densityQ inEquation (6.92), <strong>and</strong> it consists of the neutrons that emerge from fissions induced by the nth generation. The source is normalized to unity via division by k„. This is in accordancewith the role of k effin making the system (hypothetically) critical, as discussed in connectionwith Equation (6.81).

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