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A nuclear power plant containment sprinkler system test verification method and test device

A nuclear power plant containment and spray system technology, which is applied in the field of nuclear power plant containment spray system test verification, can solve the problems of equipment corrosion risk, high humidity in the workshop, complex protection measures, etc., and achieve the effect of avoiding corrosion risk

Active Publication Date: 2019-11-05
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

When the conventional on-site spraying method is used, complex protection measures need to be taken for the equipment in the factory before the test, and at the same time, the humidity in the factory building is high after the test, which brings corrosion risks to the equipment

Method used

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  • A nuclear power plant containment sprinkler system test verification method and test device
  • A nuclear power plant containment sprinkler system test verification method and test device
  • A nuclear power plant containment sprinkler system test verification method and test device

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Embodiment 1

[0025] A nuclear power plant containment sprinkler system test verification method, comprising the following steps:

[0026] Establish the flow-pressure difference relationship of a single nozzle: establish a single nozzle test system under the natural injection state, and obtain the flow rate W of the nth nozzle through the test n and the pressure P before the nozzle n , pressure difference between nozzle inlet and outlet ΔP n By the formula ΔP n =P n -P atm Calculated to get, P atm Atmospheric pressure, establish the nozzle flow-pressure difference relationship formula according to the test data, replace the nozzle, repeat the above process, and obtain the flow-pressure difference relationship formula of all nozzles;

[0027] Obtain the relationship between the total flow rate of the nozzle and the pressure difference: couple the flow-pressure difference relationship of all the nozzles in the natural injection state to obtain the total flow of the nozzle - the pressure ...

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Abstract

The invention discloses a test and verification method for the containment spray system of a nuclear power plant, which comprises the following steps: establishing the flow-pressure difference relationship of a single nozzle; obtaining the total flow-pressure difference relationship of the nozzle in the spray loop to be verified; Sprinkler branch flow-pressure difference relational expression; combining the spray head total flow-pressure difference relational expression in the spray circuit to be verified and the spray branch flow-pressure difference relational expression can be solved to obtain the flow rate of the spraying branch to be verified and nozzle pressure differential. The present invention can obtain the flow of the spray branch of the containment spray system (that is, the flow of the spray pump of the spray branch) without modifying the original structure in the plant and avoiding the risk of corrosion to the equipment in the containment of the nuclear power plant. , nozzle inlet and outlet pressure difference and other spray characteristics, providing data support for the functional verification of the nuclear power plant containment sprinkler system.

Description

technical field [0001] The invention relates to the field of nuclear power plant containment spray system tests, in particular to a nuclear power plant containment spray system test verification method. Background technique [0002] The containment sprinkler system is a safety system of a nuclear power plant. In the event of a design basis accident such as a leakage of the primary circuit or a rupture of the steam pipeline in the containment, the spray system sprays boric acid solution and chemical reagents into the containment to reduce the ambient temperature and During the commissioning of the nuclear power plant, it is necessary to carry out the containment spray test to check whether the spray characteristics such as the flow rate of the spray branch and the pressure difference between the inlet and outlet of the nozzle meet the design requirements. When the conventional on-site spraying method is used, complex protection measures must be taken for the equipment in the ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01N17/00
CPCG01N17/00
Inventor 谢添舟李勇谢士杰幸奠川郑华赵海江
Owner NUCLEAR POWER INSTITUTE OF CHINA