Neutron flux uncertainty quantification method and system, computer equipment and medium

Abstract

The invention relates to a neutron flux uncertainty quantification method and system, computer equipment and a medium. The method comprises the following steps: S1, acquiring uncertainty input parameters; calculating parameters of the target reactor in different states are output according to the uncertainty input parameters; the calculation parameters comprise reactor core neutron flux output parameters; s2, the calculation parameters and the power of the target reactor serve as response parameters, and the neutron flux uncertainty is obtained through calculation. According to the method, the model uncertainty and the measurement uncertainty related to the neutron flux are enveloped by acquiring the uncertainty input parameter and combining the power as the response parameter, so that an operator can more accurately know the real state of the reactor.

Description

technical field [0001] The invention relates to the nuclear data quantification field of nuclear reactor core, in particular to a neutron flux uncertainty quantification method, system, computer equipment and storage medium. Background technique [0002] In some large pressurized water reactors, a fixed self-powered neutron detector system (SPND) is used for flux map measurement. To confirm the uncertainty of SPND measurement results, it is necessary to quantify the neutron flux at the position of the SPND probe in advance. Measurement uncertainty and SPND probe sensitivity uncertainty, both are indispensable. [0003] Among them, the uncertainty of SPND probe sensitivity can be quantitatively analyzed by experimental piles, but neutron flux is not a neutronics parameter that can be directly measured, so it is not possible to simply use experimental methods for quantitative analysis of uncertainty. [0004] In addition, since the model uncertainty and measurement uncertaint...

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Problems solved by technology

[0004] In addition, since the model uncertainty and measurement uncertainty cannot be obtained by pure theoretical calculation, the method of simply adopting the forward transfer method of theoretical calculation uncertainty cannot quantify the neutron flux at the position of the SPND probe

[0005] At present, in some schemes, the method of quantifying neutron flux uncertainty based on experimental values ​​often obtains an envelope value, and it is impossible to accurately obtain each uncertainty. Considering that the new reactor type lacks experimental data, strictly speaking the method is not applicable

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