Experimental device for the study of two-phase flow instability and alternating thermal stress between tube bundles under load shedding disturbance

Abstract

The invention aims at providing an interbank two-phase flow instability and alternating heat stress research testing device under load shedding disturbance. A preheater and a vapor-water separator are installed at the two ends of an experimental section respectively, a water storage tank is respectively connected with a condenser and the preheater through pipes, the preheater is connected with the experimental section through a high-pressure pump, and a self-reliance type pressure flow combination valve is installed at an outlet of the experimental section. A double-end conducting probe, a pressure sensor, an orifice plate flowmeter, a stress strain gage and a sheathed thermocouple are installed on the experimental section. According to the interbank two-phase flow instability and alternating heat stress research testing device under load shedding disturbance, the method that primary side high-temperature high-pressure fluid is used for heating secondary side fluid is used, a U-type bank of the experimental section is arranged in a square mode, the characteristics of actual vapor-liquid two-phase flow of a vapor generator can be well reflected, the temperature and stress of the same position are measured, change rules of stress strain of a heat transmitting pipe are researched under the joint effect of the external force and the temperature, and a damage mechanism of the heat transmitting pipe of the vapor generator under specific disturbance caused by load shedding is disclosed.

Description

technical field [0001] The invention relates to a test device, in particular to a two-phase flow test device. Background technique [0002] The steam generator is the key equipment for heat exchange in the primary and secondary circuits of nuclear power. The wall thickness of the heat transfer tube is only about 1mm, which is the weakest link in the pressure boundary of the primary circuit. Due to the influence of ship maneuverability requirements and steam turbine load rejection conditions, the operating power of marine nuclear power steam generators changes frequently and in a large range. The periodic alternation of thermal stress leads to stress damage of the heat transfer tube. Alternating thermal stress is not only affected by the flow instability of vapor-liquid two-phase flow alone, but also closely related to heat transfer deterioration phenomena such as boiling crisis and critical heat load. When the boiling heat transfer deteriorates, the surface of the heat tra...

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Problems solved by technology

However, there is no published literature on the study of two-phase flow instability and alternating thermal stress under load rejection conditions, and there is no ready-made experimental device that can realize related functions

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