Fission source extrapolation method for accelerated Monka criticality calculation
A push method and Monte Carlo technology, applied in the field of reactor engineering, can solve problems such as slow convergence of fission sources, and achieve the effects of improving critical calculation efficiency, good application effects, and accelerating the convergence of fission sources
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[0019] like Figure 4 As shown, the fission source extrapolation method for accelerating the Monte Carlo calculation of the Monte Carlo criticality involved in this embodiment can significantly accelerate the convergence speed of the fission source during the Monte Carlo calculation of the reactor, thereby improving the criticality calculation efficiency.
[0020] Step 1: The neutron transport equation needs to be solved in the reactor criticality calculation: Among them: L, C, S and M are the 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 the iterative operator, which reflects the global response relationship process of the fission reaction, and a series of eigenvalues of F are |k 0 |>|k 1 |>|k 2 |>....
[0021] Step 2: When performing the Monte Carlo critical calculation, first set the initial fission sour...
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