Fission source extrapolation method for accelerating Monte Carlo critical calculation
A push method and Monte Carlo technology, applied in the field of reactor engineering, can solve the problems of slow convergence of fission sources, etc., and achieve the effects of improving critical calculation efficiency, good application effects, and accelerating the convergence of fission sources
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[0019] Such as Figure 4 As shown, it is a fission source extrapolation method for accelerated Monte Carlo critical calculation involved in this embodiment, which can significantly accelerate the fission source convergence speed in reactor Monte Carlo calculation, thereby improving the efficiency of critical calculation.
[0020] Step 1: The neutron transport equation needs to be solved in the reactor criticality calculation: Among them: L, C, S and M are leakage term, absorption term, scattering term and fission term respectively, k eff is the effective multiplication factor, ψ is the neutron flux density, and its fission iteration satisfies: Among them: F is an iterative operator, which reflects the global response relationship process of fission reaction, and a series of eigenvalues of F are |k 0 |>|k 1 |>|k 2 |>···.
[0021] Step 2: When performing Monte Carlo critical calculation, first set the initial fission source, the deviation between the initial fission sou...
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