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Monitoring method and system for leakage at pressure boundary of primary coolant system in nuclear power station

A monitoring system and technology for nuclear power plants, applied in the field of radiation leakage monitoring of nuclear power plants, can solve problems such as leakage of the pressure boundary of the primary circuit, and achieve the effect of ensuring safe operation, fast and reliable monitoring

Active Publication Date: 2012-04-25
中广核工程有限公司 +1
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  • Abstract
  • Description
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Problems solved by technology

[0014] Aiming at the defect that the existing nuclear power plant containment atmospheric radiation monitoring system fails to monitor aerosol, iodine and inert gas quickly and accurately to monitor the leakage of the pressure boundary of the primary circuit, a method and system for monitoring the pressure boundary leakage of the primary circuit of the nuclear power plant are provided

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  • Monitoring method and system for leakage at pressure boundary of primary coolant system in nuclear power station
  • Monitoring method and system for leakage at pressure boundary of primary coolant system in nuclear power station
  • Monitoring method and system for leakage at pressure boundary of primary coolant system in nuclear power station

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Embodiment Construction

[0053] The method and system for monitoring the pressure boundary leakage of the primary circuit of the core station of the present invention will be further explained and described below in conjunction with the drawings and embodiments.

[0054] figure 2 It is a structural diagram of the first embodiment of the system of the present invention, such as figure 2 As shown, in the first embodiment, the system of the present invention includes:

[0055] A sample control device 301, which is arranged in the containment vessel 200, and is used to obtain atmospheric samples in the pressure boundary area of ​​the primary circuit;

[0056] Fluorine 18 detection device 302, which is arranged outside the containment vessel 200, is connected to the sample control device 301 through a pipeline, and is used to receive the atmospheric sample obtained by the sample control device 301, and perform filtration and radiation measurement on the aerosol in the atmospheric sample to detect The c...

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Abstract

The invention relates to a monitoring method and system for leakage at pressure boundary of a primary coolant system in a nuclear power station. The monitoring system comprises a sample control device, a fluorine-18 detection device, a first pressure gauge, a thermometer, a first processor and a first sampling pump, and acquires an atmosphere sample at a pressure boundary area of the primary coolant system so as to measure specific activity of fluorine-18 existing in the atmosphere sample in the form of aerosol and determine whether there is leakage at pressure boundary of the primary coolant system through comparison of the measured specific activity with a preset threshold value. The invention also discloses a monitoring method for leakage at pressure boundary of the primary coolant system in the nuclear power station; according to the method, specific activity of fluorine-18 existing in the atmosphere sample obtained at the pressure boundary area of the primary coolant system is measured and compared with the preset threshold value so as to determine whether there is leakage at pressure boundary of the primary coolant system. The system and method provided in the invention can accurately and reliably monitor whether there is leakage at pressure boundary of the primary coolant system under the condition of meeting related requirements of U.S. Nuclear Regulatory Commission.

Description

technical field [0001] The invention relates to radiation leakage monitoring of nuclear power plants, and more specifically relates to a method and system for monitoring pressure boundary leakage of a primary circuit of a nuclear power plant. Background technique [0002] Nuclear power plants rely on the fission energy released by the fission of radioactive materials to generate electricity. The nuclear fuel continuously undergoes chain fission reactions in the reactor pressure vessel, releasing a large amount of heat energy. The heat energy is brought to the steam generator by the coolant circulating in the primary circuit, so that the circulating water in the secondary circuit is vaporized, thereby driving the steam turbine to do work. When a nuclear power plant is in normal operation, the coolant in the primary circuit is usually in a state of high temperature and high pressure. Once the pressure boundary of the primary circuit leaks, it will cause a large amount of vapo...

Claims

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Application Information

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IPC IPC(8): G21C17/07
CPCY02E30/30
Inventor 陈冬雷王骄亚刘东波张龙强张瑜
Owner 中广核工程有限公司
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