Method and system for testing nuclear power station pipeline leakage rate

Abstract

The invention relates to a method and a system for testing nuclear power station pipeline leakage rate. The method includes: generating corresponding media with a medium generator; measuring medium mass through a mass flowmeter; cooling media, which is mixed by a mixer and flowed out from a test section, with a condensing device, measuring the media with the mass flowmeter, comparing measured mass with input mass, and regarding the measuring result as creditable if measured mass equals to or is close to the input mass; otherwise, repeating the test; and cutting open the test section, detecting crack surface roughness and a runner, using the detecting value as input of a leakage rate program, and comparing difference between the result of the leakage rate program and the measuring result. Crack size is simulated to build relation of flow and defined size, leakage test under actual working conditions can be performed aiming at actual cracks, and leakage amount of different load and crake forms can be measured.

Description

technical field [0001] The invention relates to a nuclear power plant pipeline leakage test technology, in particular to a test method and system for the nuclear power plant pipeline leakage rate. Background technique [0002] When a leak occurs in a pressure pipeline of a nuclear power plant, the high-temperature and high-pressure fluid is sprayed outward from the breach of the pipeline to the low-pressure environment, the fluid pressure drops rapidly, and the working fluid changes from a single-phase supercooled state to a two-phase state rapidly, and there is an obvious gap between the gas-liquid phase. The heat and power are unbalanced, and the working medium becomes critical flow at the end of the breach, and the mechanism is very complicated. Therefore, it is necessary to study a quantitative test method and device for the leakage rate of high-pressure fluid penetrating cracks and critical leaks, so as to correct the calculation model of the leakage rate of pipeline pe...

AI Technical Summary

Problems solved by technology

[0003] Aiming at the problems of great difficulty and uncertainty in the quantitative measurement of crack flow rate and crack size in the prior art, the present invention provides a test method for the leakage rate of nuclear power plant pipelines in combination with the existing experimental conditions and actual engineering needs And the system mainly adopts the form of simulating the crack size to establish the relationship between the flow rate and the determined size. At the same time, the leakage test under the actual working conditions is carried out for the real cracks in the actual project, and the leakage under different crack forms under different loads can be measured.

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