Reactor embedded resonance self-shielding calculation method

Abstract

A reactor embedded resonance self-shielding calculation method includes two main steps of 1 calculation based on the resonance section of a one-dimensional fuel lattice cell and 2 embedded iteration calculation based on stationary source calculation and interpolation calculation. The step 1 is executed first to obtain a geometric related resonance section list, the resonance section list is designed according to geometry of the actual reactor fuel lattice cell and is used for replacing a conventional resonance section list in an original multigroup nuclide section database so as to generate an improved multigroup nuclide cross section database, and the step 2 is executed based on the improved multigroup nuclide cross section database to obtain effective resonance self-shielding sections of all regions in a reactor finally; the step 2 is a body of embedded resonance calculation, and the step1 provides a necessary resonance database for the step 2. As transport solution of a single-group stationary source is used for considering influence on the resonance self-shielding effect by reactor inhomogeneous geometry, resonance calculation is embedded into the transport calculation process, and consistency with transport calculation results is achieved.

Description

technical field [0001] The invention relates to the field of nuclear reactor physical calculations, in particular to a reactor embedded resonance self-screen calculation method. Background technique [0002] Resonance self-shielding calculation is an important part of reactor physics calculation. The main task of calculation is to provide effective multi-group cross-section for transport calculation. Effective multi-group cross-section can ensure the conservation of neutron reaction rate in transport calculation. The effective multi-group cross-section is calculated by merging the continuous energy cross-section according to the weight of the energy spectrum. Because the continuous energy neutron reaction cross section of the main fission nuclide of the reactor has a resonant peak in the thermal neutron energy region, the energy spectrum in this energy region has a depression corresponding to the resonant peak, and the neutron flux density decreases, forming a neutron sub-s...

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Problems solved by technology

[0004] In order to solve the problems existing in the existing resonance self-shielding calculation method, the present invention proposes a reactor embedded resonance self-shielding calculation method, which uses the characteristic line method to perform fixed source transport calculation on the non-uniform geometry of the reactor to obtain a relatively Good geometric adaptability; for the resonant fuel area, calculate its background cross-section, and perform interpolation calculation on the resonance cross-section table in the multi-group database, which has high calculation efficiency; at the same time, the resonance cross-section table used in this method is calculated simply dimensional fuel cell problem, this treatment makes the resonance self-shielding calculation have higher accuracy; in the whole process, because of the use of single-group stationary source transport solution to consider the influence of reactor non-uniform geometry on the resonance self-shielding effect , the resonance calculation is embedded in the transport calculation process, which is consistent with the transport calculation results

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