Quantitative analysis method and device for result uncertainty of reactor core thermal hydraulic program

Abstract

The invention provides a quantitative analysis method and device for result uncertainty of a reactor core thermal hydraulic program, and relates to the technical field of nuclear reactor core channelprogram model uncertainty quantification. The method comprises the steps: when target parameters of a to-be-evaluated sub-channel program model are obtained, determining influence input parameters ofthe target parameters based on a variance decomposition method, and further determining uncertainty distribution of the influence input parameters, and performing the sampling of the uncertainty distribution to obtain a plurality of sampling values; calculating an influence input parameter value corresponding to each sampling value; respectively inputting the plurality of influence input parametervalues into the to-be-evaluated sub-channel program model to obtain a result value of a target parameter corresponding to the influence input parameter; calculating the uncertainty of the target parameter according to the plurality of result values; and accurately estimating the sub-channel program model through the calculated uncertainty. Moreover, the calculated amount of uncertainty calculation is greatly reduced, and the analysis efficiency is improved.

Description

technical field [0001] The invention relates to the technical field of uncertainty quantification of a nuclear reactor core sub-channel program model, in particular to a method and device for quantifying the uncertainty of a core thermal-hydraulic program result. Background technique [0002] With the development of computer technology, in order to better understand energy systems such as power systems and thermal systems, computer technology can be used to establish corresponding mathematical models for research. However, mathematical models cannot completely and accurately simulate actual physical processes. Therefore, it is necessary to evaluate and analyze the established mathematical model before using the mathematical model to conduct experiments. [0003] At present, FFTBM (Fast Fourier Transform Method) method, DIPE (Drtermination of Input Parameters Empirical Properties) method, CIRCE′ (Calcul des Incertitudes Relatives aux Corre′lations E′lementaires) method and T...

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Problems solved by technology

[0002] With the development of computer technology, in order to better understand energy systems such as power systems and thermal systems, computer technology can be used to establish corresponding mathematical models for research. However, mathematical models cannot completely and accurately simulate actual physical processes. Therefore, it is necessary to evaluate and analyze the established mathematical model before using the mathematical model to conduct experiments.

[0003] At present, FFTBM (Fast Fourier Transform Method) method, DIPE (Drtermination of Input Parameters Empirical Properties) method, CIRCE′ (Calcul des Incertitudes Relatives aux Corre′lations E′lementaires) method and The MCDA (Model Calibration through Data Assimilation) method, the above-mentioned method is not yet mature in the analysis of the nuclear reactor core, and still has the disadvantages of limited number of mathematical model parameters that can be evaluated, and a large amount of calculation, which reduces the analysis efficiency

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