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A method and device for measuring the leakage rate of a nuclear power plant circuit

A leak rate, nuclear power plant technology, applied in the field of data processing, can solve problems such as calculation errors and heavy workload, and achieve the effect of improving measurement efficiency

Active Publication Date: 2019-09-17
FUJIAN NINGDE NUCLEAR POWER +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The inventors found that at present, the above-mentioned test requires the measurement personnel to manually read the meter and perform calculations, which has a large workload and the risk of calculation errors. Therefore, it is very necessary to provide a system for automatically detecting the leakage rate

Method used

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  • A method and device for measuring the leakage rate of a nuclear power plant circuit
  • A method and device for measuring the leakage rate of a nuclear power plant circuit
  • A method and device for measuring the leakage rate of a nuclear power plant circuit

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Experimental program
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Effect test

Embodiment 1

[0043] Such as figure 1 As shown, a method for measuring the leakage rate of a nuclear power plant circuit provided by Embodiment 1 of the present invention includes:

[0044] S1: Obtain the water volume of the volume control tank of the chemical and volume control system;

[0045] S2: Calculate and obtain the leakage rate of the circuit according to a preset formula.

[0046] Wherein, step S1 can be realized by collecting the value read by the sensor for measuring the water level in the volume control box, but the solution is not limited to this implementation manner. The preset formula can be set according to actual detection requirements, and here, it is not limited to a specific formula, and those skilled in the art can program according to actual needs.

[0047] It can be seen that this scheme can automatically detect the leakage rate of the coolant of the reactor, and improves the measurement efficiency compared with manual calculation.

Embodiment 2

[0049] Specifically, such as figure 2 As shown, the method for measuring the leakage rate of the nuclear power plant circuit provided by this embodiment can also be the steps:

[0050] S1: Obtain the water volume of the volume control tank of the chemical and volume control system;

[0051] S2: Calculate and obtain the leakage rate of the circuit according to a preset formula.

[0052] Wherein, step S1 can be realized by collecting the value read by the sensor for measuring the water level in the volume control box, but the solution is not limited to this implementation manner. The preset formula can be set according to actual detection requirements, and here, it is not limited to a specific formula, and those skilled in the art can program according to actual needs.

[0053] S3: Judging whether the calculated circuit leakage rate is greater than a preset value, if yes, output a first judgment result, if not, output a second judgment result.

[0054] Wherein, when the leak...

Embodiment 3

[0057] Specifically, such as image 3 As shown, the method for measuring the leakage rate of the nuclear power plant circuit provided by this embodiment can also be:

[0058] S1: Obtain the water volume of the volume control tank of the chemical and volume control system;

[0059] S2: Calculate and obtain the leakage rate of the circuit according to a preset formula.

[0060] Wherein, step S1 can be realized by collecting the value read by the sensor for measuring the water level in the volume control box, but the solution is not limited to this implementation manner. The preset formula can be set according to actual detection requirements, and here, it is not limited to a specific formula, and those skilled in the art can program according to actual needs.

[0061] S3: Judging whether the calculated circuit leakage rate is greater than a preset value, if yes, output a first judgment result, if not, output a second judgment result.

[0062] Wherein, when the leakage rate is...

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Abstract

The invention provides a measurement method for a circuit leakage rate of a nuclear power plant. The circuit leakage rate is obtained through the steps of obtaining the water quantity of a volume control tank of a chemical and volume control system and carrying out calculation according to a pre-set formula. The measurement method provided by the invention can be used for automatically detecting the leakage rate of a coolant of a reactor; and the measurement efficiency is improved while compared with that of manual calculation.

Description

technical field [0001] The invention relates to the technical field of data processing, in particular to a method and device for measuring the leakage rate of a nuclear power plant circuit. Background technique [0002] With the continuous increase of electricity consumption information and the continuous improvement of customer basic information, the power information data shows an explosive growth trend. [0003] Among them, the pressurized water reactor nuclear power plant needs to measure the leakage rate of the reactor coolant every day to ensure the safe operation of the nuclear power plant. Specifically, the leakage rate of the reactor coolant is measured by measuring the change of the water volume in the chemical and volume control system, and then measuring the leakage of the reactor coolant. [0004] The inventors found that, at present, the above-mentioned test requires the measurement personnel to manually read the meter and perform calculations, which requires ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00
CPCG21C17/002Y02E30/30
Inventor 熊叶寒黄维哲潘烽李晋高志远
Owner FUJIAN NINGDE NUCLEAR POWER