Correction method considering influence of local structure in reactor core flow field calculation

Abstract

The invention discloses a correction method considering the influence of a local structure in reactor core flow field calculation, which can add the influence of a positioning grid on a local flow field to overall flow field calculation for correction when performing three-dimensional thermal hydraulic calculation on a fuel assembly with the positioning grid. The correction process comprises the following steps: 1, determining a correction area; 2, establishing a calculation region geometric model; 3, performing hydraulics analysis of a local flow field; 4, calculating an influence range and an influence factor; and 5, substituting into overall calculation for correction. According to the method, the defect that an existing reactor core flow field three-dimensional analysis program difficultly reflects a local flow field near the positioning grillwork can be overcome, and the accuracy of a result obtained through numerical calculation is improved; the successful establishment of the local flow field correction method can be suitable for various computational fluid mechanics analysis programs to carry out numerical simulation on various rod bundle / tube bundle channels containing similar structures under different working conditions to obtain a calculation result capable of reflecting a local flow field near a local structure; and the correction method is also suitable for similar working conditions of other similar equipment.

Description

technical field [0001] The invention belongs to the technical field of three-dimensional thermal-hydraulic characteristic analysis of key equipment in nuclear power plants, and in particular relates to a correction method for considering the influence of local structures in the calculation of reactor core flow field. Background technique [0002] During the operation of a nuclear power plant, the ability of the coolant in the reactor core to cool the fuel assembly is one of the important criteria for measuring the safety and economy of a nuclear power plant. Therefore, it is of great significance to analyze the flow heat transfer characteristics of the reactor core and obtain its internal thermal and hydraulic parameters for the design and maintenance of nuclear power plants. In the early research work, the reactor core was generally studied by dividing the nodes by one-dimensional method. With the broadening of research fields and the maturity of technical means, three-dim...

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Problems solved by technology

[0007] In order to overcome the above-mentioned problems in the prior art, the purpose of the present invention is to provide a correction method that considers the influence of local structures in the calculation of the reactor core flow field, which can improve the existing three-dimensional analysis program of the core flow field that cannot reflect the positioning grid. The defects of the nearby local flow field improve the accuracy of the results obtained by numerical calculation; the successful establishment of the local flow field correction method of the present invention can be applied to various types of computational fluid dynamics analysis programs for various rod bundles / Numerical simulation of the tube bundle channel is carried out under different working conditions to obtain calculation results that can reflect the local flow field near the local structure; this correction method is also applicable to similar working conditions of other similar equipment

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