Visual measurement experiment device of critical heat flux density of integrally sintered rectangular narrow slit channel

Abstract

The invention discloses a visual measurement experiment device of critical heat flux density of an integrally sintered rectangular narrow slit channel. The visual measurement experiment device comprises a conductive circuit formed by an inlet end copper row, a heating plate, and an outlet end copper row, a fluid flow channel composed of an inlet channel, an inlet buffer cavity, a rectangular narrow slit channel, an outlet buffer cavity, and an outlet channel, a rectangular narrow slit channel formed by a heating plate embedded in a groove of an integrally sintered ceramic substrate and a stainless steel plate embedded with a quartz glass and withstanding the impact of gas-liquid two-phase fluids with high temperature and high pressure, a pressure measuring assembly embedded in the integrally sintered ceramic substrate for measuring relevant experimental parameters, and a thermocouple assembly. The fluid passes the inlet channel and the inlet buffer cavity, and then enters the rectangular narrow slit channel. A boiling critical phenomenon occurs after the fluid is heated in the rectangular narrow slit channel. The movement behavior of vapor phase can be effectively observed throughthe quartz glass when boiling critical occurs in the channel. the occurrence of the critical boiling phenomenon is judged through the vapor phase movement behavior and the temperature information of the thermocouple. An experiment guarantee condition is provided for the mechanism of deeply researching the critical boiling phenomenon in the rectangular narrow slit channel.

Description

technical field [0001] The invention belongs to the field of gas-liquid two-phase flow heat transfer, and in particular relates to an experimental device for visually measuring the critical heat flux density of an integrally sintered rectangular narrow slit channel. Background technique [0002] The critical heat flux is the most important thermal-hydraulic limiting parameter to ensure the safety of the reactor core. When the critical boiling phenomenon occurs, the flow boiling mechanism of the coolant changes, the heat transfer coefficient decreases, the heat transfer performance of the fuel element surface deteriorates, and the wall temperature rises. The fuel elements can burn out and cause radioactive leakage. Therefore, the accurate prediction of critical heat flux is of great significance for reactor design and safety analysis, which can provide a basis for design and guarantee the safe operation of heat transfer equipment. [0003] Rectangular slit channel is an impo...

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Problems solved by technology

[0005] At present, no published experimental device has been found fo...

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