A method and device for calculating the leakage rate of a check valve

A check valve and leakage rate technology, applied in the field of automatic control, can solve the problems of meaningless check valve results and achieve the effect of avoiding negative values

Active Publication Date: 2020-01-31
FUJIAN NINGDE NUCLEAR POWER +1
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Problems solved by technology

[0015] This application provides a method and device for calculating the leakage rate of a check valve, with the purpose of solving the problem that the results obtained by the existing check valve leakage rate detection method are meaningless

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  • A method and device for calculating the leakage rate of a check valve
  • A method and device for calculating the leakage rate of a check valve
  • A method and device for calculating the leakage rate of a check valve

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Embodiment Construction

[0046]In the process of research, the inventor found that the negative value in the test was due to the unsatisfied test conditions. The test is required to be carried out under the condition that the temperature of RCP and RRA is stable, but in the uplink stage of the unit, the temperature of the first circuit and the RRA system before the test are both about 170°C, and the RRA system is cooled to below 60°C after isolation, while the RCP121 / 221 / 321VP The temperature in the upstream test area is still about 170°C. When the test is carried out 6 hours later, the RRA system and the primary circuit have not reached temperature equilibrium, which does not meet the test conditions. Test at this time, the first and third loops will transfer heat to the RRA system, causing the temperature in the closed space to drop, and the liquid shrinkage rate in the space is very large, exceeding the leakage rate of the check valve, so that the pressure in the closed space does not rise but rever...

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Abstract

The application provides a method and a device for calculating the leakage rate of a check valve. For a situation in which heat balance is not achieved between a closed space of which the boundary includes a check valve under test and the outside, curve fitting is carried out according to the change data of the pressure in the closed space with time, the change factors of the water volume of the closed space caused by the heat transfer between the closed space and the outside are excluded according to the curve to obtain the pressure change rate of the closed space caused by the leakage of thecheck valve under test, and the leakage rate of the check valve under test is obtained according to the pressure change rate. As the leakage rate of the check valve is obtained through curve fitting,the influence of the heat transfer between the closed space and the outside on the test result can be excluded. Therefore, the test result is closer to the real value than the data obtained when thetemperature is not stabilized, and the problem that a negative test result is invalid or a large test result is unsatisfactory is avoided.

Description

technical field [0001] The present application relates to the field of automatic control, in particular to a method and device for calculating the leakage rate of a check valve. Background technique [0002] For nuclear power plants, the three major functions (also known as the three elements) to ensure nuclear safety include: reactivity control, core cooling and containment of radioactive products. Among them, three barriers are set up in the pressurized water reactor nuclear power plant: the fuel element cladding, the pressure boundary of the primary circuit and the reactor building (containment vessel). After an accident, the system used to limit the consequences of the accident and restore the reactor to a reliable safe state is called an engineered safety feature. The Security Injection System (system code RIS) is one of them. When a breach event or accident occurs in the primary or secondary circuit, the RIS injects boron-containing water into the primary circuit, in...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01M3/28
CPCG01M3/2876
Inventor 姚士佳王中良
Owner FUJIAN NINGDE NUCLEAR POWER
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