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Appraisal platform and method for mechanical seals of reactor coolant pumps in mega-kilowatt nuclear power plants

A nuclear power plant reactor, mechanical seal technology, applied in mechanical equipment, liquid variable capacity machinery, pump testing and other directions, to achieve the effect of saving costs, facilitating safe production, and improving the ability of fault diagnosis and analysis

Active Publication Date: 2011-12-14
GUANGDONG NUCLEAR POWER JOINT VENTURE +3
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, the seal identification technology and test equipment of the refurbished main pump need to be improved and perfected

Method used

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  • Appraisal platform and method for mechanical seals of reactor coolant pumps in mega-kilowatt nuclear power plants
  • Appraisal platform and method for mechanical seals of reactor coolant pumps in mega-kilowatt nuclear power plants
  • Appraisal platform and method for mechanical seals of reactor coolant pumps in mega-kilowatt nuclear power plants

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Experimental program
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Effect test

Embodiment 1

[0053] figure 1 It is a block diagram of the identification platform, where the dotted line is the transmission path of the control signal, and the solid line is the flow path of the circulating water. This embodiment 1 is mainly applied to the functional appraisal of the 8-inch No. 1 seal of the CPR1000 main pump.

[0054] The main pump mechanical seal appraisal platform includes a seal appraisal test bench 2 and a control host 1 for controlling the seal appraisal test bench. The control host 1 is used to control various test parameters of the seal qualification test bench 2. The sending of the control signal is realized by the software installed in the control host 1. These software mainly include the mechanical seal refurbishment program, mechanical seal test program, and mechanical seal inspection. Standard procedures and test acceptance criteria procedures, all control is realized through the human-computer interaction interface of the control host 1, without the need fo...

Embodiment 2

[0064] A method for identifying the mechanical seal of a reactor coolant pump in a million-kilowatt nuclear power plant, using the identification platform of Embodiment 1, comprising the following steps:

[0065] 1) Replace the static O-ring in the mechanical seal

[0066] Before appraising the mechanical seal, it is necessary to replace the aging static O-ring in the mechanical seal, and then appraise the mechanical seal after replacing the static O-ring.

[0067] 2) Determination of sealing characteristics in stable working conditions

[0068] Include the following sub-steps:

[0069] 2.1), input the pressure difference and temperature parameters under stable working conditions on the control host 1;

[0070] 2.2) Record the leakage of the mechanical seal under the pressure difference and temperature parameters of the above stable working conditions.

[0071] 3) Determination of high temperature sealing leakage characteristics

[0072] Include the following sub-steps:

...

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Abstract

The invention discloses a mechanical seal appraisal platform and method for a reactor coolant pump of a million-kilowatt nuclear power plant. The appraisal platform includes a seal appraisal test bench and a control host for controlling the seal appraisal test bench; the seal appraisal test bench includes A pump unit module, a refrigeration unit module and a sealing test module, the sealing test module is used to measure the stable working condition sealing characteristics, high temperature sealing leakage characteristics, cold state characteristics, pressure hysteresis transient characteristics and static sealing characteristics of the mechanical seal. The identification method includes the step of replacing the O-ring in the mechanical seal and several characteristic determination steps: stable working condition seal, high temperature seal leakage, pressure hysteresis transient, cold state and static seal. The ability of fault diagnosis and analysis of reactor coolant pump mechanical seal is improved, which not only saves cost, but also can carry out theoretical research work on various characteristics of seal under various working conditions, so as to facilitate safe production.

Description

technical field [0001] The invention relates to a key technology in a reactor coolant pump of a million-kilowatt nuclear power plant, and more specifically, relates to a mechanical seal identification platform and method for a reactor coolant pump of a million-kilowatt nuclear power plant. Background technique [0002] The function of the mechanical seal of the reactor coolant pump of a million-kilowatt nuclear power plant (hereinafter referred to as "main pump") is to ensure the sealing of the medium. Among them, the No. 1 seal bears almost all the pressure difference of 15.5MPa in the primary circuit, and is the main seal in the tertiary seal. EDF has counted 19 cases of abnormal leakage of the No. 1 shaft seal of the main pump in French nuclear power plants, of which 6 cases were caused by the continuous increase of the No. 1 seal leakage of the main pump, which led to unplanned shutdown of the unit or early overhaul. In view of the fact that the No. 1 seal is a non-cont...

Claims

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Application Information

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IPC IPC(8): F04B51/00
Inventor 毛文军吴粉山刘军生孙维伊张春旺黎志政王寅初
Owner GUANGDONG NUCLEAR POWER JOINT VENTURE
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