Scalable rod bundle channel multi-physical field visual body design

Abstract

The invention discloses a scalable rod bundle channel multi-physical field visual body design, consisting of six parts, i.e., a visual body barrel used for shooting a longitudinal section, an upper seal head used for shooting a cross section in an overlooking way, a lower part transition section having scalability, a lower seal head connected with an experimental loop, a visual experiment rod bundle, a rod bundle fastening piece used for tensioning the experiment rod bundle, and related matching flange plates. An experimental body is formed by bonding acrylic, can be used for carrying out a rod bundle channel multi-physical field visual experiment under the normal pressure, and simulates the flowing condition of a reactor core. After the scalable rod bundle channel multi-physical field visual body design is adopted, shooting is performed respectively on the top face and the four side faces, so that overall real-time measurement is realized; the shooting content is diverse. The design provided by the invention is ingenious; the visual rod bundle is straightened and fixed by means of the rod bundle fastening piece; the rod bundle fastening piece is reasonable in design; a telescopic corrugated pipe is adopted as the lower part transition section, so that the body is enabled to be safe and reliable. The scalable rod bundle channel multi-physical field visual body design is simple and compact in structure, easy in processing, convenient for observation and wide in experimental range.

Description

technical field [0001] The invention belongs to the technical field of thermal hydraulics of reactors, and in particular relates to a scalable rod bundle channel multi-physics field visualization body design applied to multi-physics field information measurement of velocity, concentration and temperature in a rod bundle channel. Background technique [0002] The fuel assembly is an important part of the pressurized water reactor core, and its internal flow and heat transfer characteristics are an important research topic in the thermal hydraulics of the reactor core. Pressurized water reactors for nuclear power plants usually use rod-shaped fuel assemblies, and their heat transfer and flow characteristics are greatly affected by the spacer grid. Due to the existence of the positioning grid, the flow mixing effect in the components will be enhanced, and the fluid in the fuel gap will generate lateral flow and vortex flow, which enhances the enhanced heat transfer process of t...

AI Technical Summary

Problems solved by technology

Zhang Junyi (a fully transparent visualization experimental device for rod bundle channels) designed an experimental body design that can be applied to high-pressure experimental conditions. However, after considering the problem of pressure bearing, there is inconvenience in the observation of the body, and it has not really achieved complete transparency. And the flow field information of the cross section cannot be observed, and the measurement of the temperature field cannot be realized

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