Reactor pressure vessel boron concentration measuring device based on modeling scaling method

Abstract

The invention provides a reactor pressure vessel boron concentration measuring device based on a modeling scaling method, which is characterized in that scaling modeling is carried out on a boron transport and diffusion behavior in a nuclear power plant reactor pressure vessel based on a similarity principle to obtain a similarity criterion of fluid flow and boric acid solution transport and diffusion behavior in RPV; designing to obtain a visual test body for simulating the RPV complex structure; based on the laser-induced fluorescence technology, a high-speed camera is used for shooting the flowing process of fluid in a complex structure of a pressure container, and the change of a concentration field in the flowing process is measured by recording fluorescence of different degrees emitted by a laser coloring agent in the fluid, so that the visual measurement and research of the concentration field under the accident safety injection condition are realized.

Description

technical field [0001] The invention specifically relates to a test device for simulating the stirring and diffusion process of boric acid solution in a reactor pressure vessel (RPV) of a nuclear power plant, which can be used for the research of boron transport and migration phenomenon in RPV and the design of structures such as nozzles in descending section and hot and cold section in RPV The optimized design, the structural size of the test device is determined by the modeling and scaling method, and the visual measurement of the mixing and diffusion process of the boric acid solution is realized by the laser-induced fluorescence technology. The technical fields involved in the present invention include fluid mechanics, reactor thermal hydraulics, etc. Background technique [0002] When a loss of water accident occurs in the reactor pipeline of a nuclear power plant, the emergency core cooling system is activated, and the high-concentration boron-containing water in the sa...

AI Technical Summary

Problems solved by technology

However, due to the complex structure of the reactor pressure vessel and the harsh accident conditions, the simplification in the numerical simulation is often difficult to completely reproduce the real flow characteristics in the RPV, so the numerical simulation method is difficult to be directly applied to the safety analysis of the boron concentration in the RPV of the nuclear power plant , it is still necessary to verify the correctness and reliability of the numerical simulation of the boron concentration in the reactor pressure vessel based on the effective flow field experimental data before engineering application

In the thermal-hydraulic experiment method, the test body mostly adopts a prototype structure or a large-scale scaled-down structure, and the measurement method is mostly an interventional single-point measurement. However, due to the lack of boron concentration information on the flow section, the parameter range is often limited when the test results are extrapolated to engineering applications

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