Nuclear power station containment vessel leakage rate monitoring method and system

A nuclear power plant containment and monitoring system technology, applied in the field of nuclear power, can solve the problems of inaccurate leakage rate and unsatisfactory calculation effect of containment leakage rate, and achieve the effect of accurate and reliable data

Active Publication Date: 2012-04-18
中广核工程有限公司 +1
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Problems solved by technology

The calculation of the containment leakage rate is mainly based on the absolute gas mass method, but the current various algorithms are different, and the calculation effect of the calculation of the containment leakage rate is not ideal
[0003] In addition, the calculated leak rate may

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  • Nuclear power station containment vessel leakage rate monitoring method and system
  • Nuclear power station containment vessel leakage rate monitoring method and system
  • Nuclear power station containment vessel leakage rate monitoring method and system

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Embodiment Construction

[0032] In order to make the object, technical solution and advantages of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described here are only used to explain the present invention, not to limit the present invention.

[0033] Such as figure 1 As shown, a nuclear power plant containment leakage rate monitoring system includes a containment vessel 1 and a central controller 2;

[0034] During the normal operation of the unit in the nuclear power plant, a pressure cycle is formed in the containment 1, which consists of a slow pressure increase process and a rapid pressure decrease process, and each cycle is about at least 15 days. Atmospheric pressure difference ΔP inside and outside the containment (ΔP = atmospheric pressure P inside the containment con - Atmospheric pressure P outside containment vessel 1 atm )...

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Abstract

The invention discloses a nuclear power station containment vessel leakage rate monitoring method, which comprises the following steps that: S1. temperature, humidity and air pressure inside a containment vessel are regularly measured and are transmitted to a central controller; S2. air injection volume is regularly measured and is transmitted to the central controller, and the standard volume variation value of the wet air is calculated by the central controller; a wet air standard volume variation curve is drawn by the central controller according to the wet air standard volume variation value at different moments, and a slope Qld is calculated; and S3. air pressure difference inside and outside the containment vessel is calculated and displayed by the central controller, and a leakage rate curve is drawn by utilizing a plurality of Qld and delta P corresponding to the Qld. The invention also discloses a nuclear power station containment vessel leakage rate monitoring system for implementing the method. Due to the adoption of the system and the method, the leakage rate inside the containment vessel is calculated according to a principle of gas mass conservation, and the data is precise and reliable.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to a method and system for monitoring the leakage rate of a containment vessel of a nuclear power plant. Background technique [0002] At present, in order to prevent the radioactive substances in the containment from escaping out of the containment, the containment of nuclear power plants needs to maintain negative pressure operation. The containment leak rate online monitoring system conducts online monitoring of the containment leak rate during unit operation, monitors changes in containment sealing, and promptly notifies the operator to take necessary actions when the leak rate reaches the operating limit. The calculation of the containment leakage rate is mainly based on the absolute gas mass method, but various algorithms are different at present, and the calculation effect of the calculation of the containment leakage rate is not ideal. [0003] In addition, the calcul...

Claims

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Application Information

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IPC IPC(8): G21C17/00G21C17/003
CPCY02E30/30
Inventor 董威刘欣李恒温小梅田亚杰
Owner 中广核工程有限公司
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