A Hybrid Calculation Method for Obtaining Few Group Section Parameters of Fast Neutron Reactor
A hybrid calculation and reactor technology, applied in the field of nuclear reactor core design and nuclear reactor physical calculation, can solve problems such as difficult to obtain results, and achieve the effect of avoiding approximation and ensuring accuracy
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[0052] Below in conjunction with accompanying drawing and specific embodiment the present invention is described in further detail:
[0053] The present invention combines the Monte Carlo method with the deterministic method, uses the Monte Carlo method to carefully consider the resonance effect of the fast reactor components, and calculates the accurate multi-group microscopic total cross-section, fission cross-section, and elastic scattering cross-section of each nuclide. The deterministic method is used to solve the elastic scattering cross sections of each order and the neutron flux moments of each order of the fast reactor components, so as to merge the multi-group cross-sections into few-group cross-sections, as shown in figure 1 Shown, this invention comprises the steps:
[0054] Step 1: For any fast reactor component to be calculated, read the geometric information of the component and the nuclide information of the corresponding material components;
[0055] Step 2: ...
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