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Method for measuring total gas content of pressurized water reactor nuclear power primary circuit

A measurement method, pressurized water reactor technology, applied in the direction of nuclear power generation, nuclear power plants, detailed information of nuclear power plants, etc., to achieve the effect of easy operation

Active Publication Date: 2020-12-18
SANMEN NUCLEAR POWER CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

At present, there are no relevant standards and analysis methods in China to measure the total gas content of the primary circuit of the PWR nuclear power plant. Coolant Total Air Content Method

Method used

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  • Method for measuring total gas content of pressurized water reactor nuclear power primary circuit
  • Method for measuring total gas content of pressurized water reactor nuclear power primary circuit
  • Method for measuring total gas content of pressurized water reactor nuclear power primary circuit

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Experimental program
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Embodiment Construction

[0053] The technical solutions of the present invention will be further described below in conjunction with the accompanying drawings and through specific implementation methods.

[0054] Such as figure 1 As shown, a method for measuring the total gas content of a pressurized water reactor nuclear power primary circuit comprises the following steps

[0055] S01 samples the coolant in the primary circuit through the sampling component. The S01 specifically includes S11 taking the sampling assembly out of the shielding shield 1, and opening the valve two 23 and the valve one 22 in the sampling assembly; S12 closing the two valves on the primary loop sampling interface, and the second fast The female connector 25 and the first quick female connector 24 are sequentially connected to the two sampling ports of the primary circuit; S13 opens the two valves on the sampling port of the primary circuit, and waits for 1 minute; S14 closes the two valves on the sampling port of the prima...

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Abstract

The invention relates to the technical field of nuclear safety and nuclear system detection, in particular to a method for measuring total gas content of a pressurized water reactor nuclear power primary circuit, which comprises the following steps: S01, sampling a primary circuit coolant through a sampling assembly; s02, measuring gas content measurement data in the sample coolant through a sample measurement assembly and a sampling assembly; and S03, calculating the total gas content of the sample coolant according to the gas content measurement data and a gas content measurement formula. The method for measuring the total gas content of the pressurized water reactor nuclear power primary loop is simple and convenient to operate, and can be used in cooperation with the measuring device to quickly and accurately measure the gas content in the primary loop, so that the degassing effect of a primary loop coolant is conveniently judged, and safe and efficient operation of a main pump isensured.

Description

technical field [0001] The invention relates to the technical field of nuclear safety and nuclear system detection, in particular to a method for measuring the total gas content of a primary circuit of a pressurized water reactor nuclear power plant. Background technique [0002] Nuclear power is one of the three pillars of electric power in the world today. At present, there are more than 400 nuclear power units in operation in more than 30 countries and regions in the world, with a total capacity of more than 300 million kilowatts; there are many types of nuclear power, such as AP1000, CPR1000, CNP1000 , ACP1000, CAP1000, etc. Among them, the pressurized water reactor nuclear power plant uses the main pump of the primary circuit to transport the reactor coolant, so that it can complete the circulation among the core, the coolant loop, and the steam generator, realize the heat transfer on the primary side, and also have the function of ensuring the safety of the core , is ...

Claims

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Application Information

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IPC IPC(8): G21C17/02G21D1/00
CPCG21C17/02G21D1/006Y02E30/00Y02E30/30
Inventor 陈东侯涛苗丽吴旭东刘高勇
Owner SANMEN NUCLEAR POWER CO LTD
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