A Calculation Method for Reactor Embedded Resonance Self-shielding

Abstract

A reactor embedded resonance self-shielding calculation method, the steps are as follows: (1) calculation based on the resonance section table of one-dimensional fuel cell; (2) embedded iterative calculation based on fixed source calculation and interpolation calculation; step (1) to obtain Geometry-dependent resonance cross-section table, the resonance cross-section table is designed according to the geometry of the actual reactor fuel cell, used to replace the conventional resonance cross-section table in the original multi-group nuclide cross-section database, resulting in an improved multi-group nuclide cross-section database, Step (2) is performed based on the improved multi-group nuclide section database to obtain the effective resonance self-shielding section of each region in the reactor; step (2) is the main body of the embedded resonance calculation, and step (1) provides the necessary Resonance database; because the present invention uses the transport solution of a single group of stationary sources 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 .

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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