Flow determination method, device and server for natural circulation loop

Abstract

The invention provides a flow determining method and device for a natural circulation loop as well as a server. The method comprises the following steps: obtaining a mathematical model of the natural circulation loop of a reactor and parameters of a coolant; according to a computational fluid dynamics principle, a reactor core heat exchange section model and a preset initial loop inlet flow rate, determining the average temperature of various sub-heat exchange section models; according to a natural circulation pressure drop balance principle, the average temperature, the reactor core heat exchange section model, a steam generator heat exchange section, a pipeline section model and the parameters of the coolant, determining a natural circulation steady-state inlet flow rate; then in combination with the natural circulation steady-state inlet flow rate and a preset rocking condition, determining the change function of the average temperature of the various sub-heat exchange section models under the rocking condition; based on a principle similar to the determining of the natural circulation steady-state inlet flow rate, determining the change function of the natural circulation inlet flow rate of the coolant under the rocking condition. According to the invention, the analysis efficiency is improved while the accuracy of the analysis result of the natural circulation flow change under the rocking condition is ensured.

Description

technical field [0001] The invention relates to the technical field of nuclear reactors, in particular to a flow determination method, device and server of a natural circulation loop. Background technique [0002] With the development of science and technology, nuclear energy, as a clean energy, has been more and more widely used in production and life. When nuclear power generation facilities such as offshore floating nuclear power plants and nuclear-powered ships operate in the ocean environment, the natural circulation system of the nuclear reactor will be affected by ocean conditions such as swaying and tilting. [0003] The existing technology is mainly through the transformation of CFD (Computational Fluid Dynamics, Computational Fluid Dynamics) software, using the transformed software to analyze the change of the natural circulation flow of the reactor under the rocking condition with time; the above transformation mainly includes the following two aspects : (1) The ...

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Problems solved by technology

However, the natural circulation loop of the reactor used in the prior art is too simple, which loses the characteristics of the reactor core. Big

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