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A device and method for detecting the water level of a nuclear power plant reactor pressure vessel

A pressure vessel and actual pressure measurement technology, which is applied in the field of nuclear safety, can solve the problems of inaccurate judgment of the degree of deterioration of the water content of the pressure vessel and the inability to directly measure the temperature of the fuel cladding.

Active Publication Date: 2017-09-01
中广核工程有限公司 +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0009] Aiming at the problems of inaccurate judgment of the degree of deterioration of the water content of the pressure vessel and the inability to directly measure the temperature of the fuel cladding when the water level measurement system of the pressure vessel fails due to a breach in the exhaust pipe or other reasons, the invention provides a method for detecting nuclear power plants. Apparatus and method for reactor pressure vessel water level

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  • A device and method for detecting the water level of a nuclear power plant reactor pressure vessel
  • A device and method for detecting the water level of a nuclear power plant reactor pressure vessel
  • A device and method for detecting the water level of a nuclear power plant reactor pressure vessel

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Embodiment 1

[0058] An embodiment of the present invention provides a device for detecting the water level of a nuclear power plant reactor pressure vessel, see figure 1 , figure 1 It is a device structure diagram of Embodiment 1 of the present invention, and the device includes:

[0059] The core cooling monitor 11 is installed in the primary circuit and connected with the pressure vessel, and is used to obtain the subcooling degree signal of the core outlet coolant and the status signal of the main pump;

[0060] The core cooling state identification module 12 is connected to the core cooling monitor 11, and is used to receive the subcooling signal and identify the temperature range where the subcooling signal is located;

[0061] The pressure vessel water level prediction module 13 is connected to the core cooling state identification module 12 and the core cooling monitor 11, receives the main pump state signal, and calculates the predicted pressure according to the temperature range ...

Embodiment 2

[0126] The implementation of the present invention provides a method for detecting the water level of the reactor pressure vessel of a nuclear power plant, which is applicable to the device for detecting the water level of the reactor pressure vessel of a nuclear power plant shown in Embodiment 1, see Figure 7 , the method includes:

[0127] Steps S01 and S02 respectively acquire the subcooling degree signal of the coolant at the core outlet and the state signal of the main pump.

[0128] In this embodiment, the existing core cooling monitor can be used to obtain the subcooling signal of the core outlet coolant and the main pump status signal, and then the core cooling state identification module receives the subcooling signal, and Identify the temperature range in which the subcooling signal is located.

[0129] Step S05, according to the temperature range of the main pump status signal and the subcooling degree signal, calculate and obtain the predicted water level of the ...

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Abstract

The invention provides a device and a method for detecting a water level of a pressure vessel of a nuclear power plant reactor. The device comprises a core cooling monitoring instrument, a core cooling state identification module and a pressure vessel water level prediction module, wherein the core cooling monitoring instrument is used for acquiring a supercooling degree signal of a cooling agent of a core outlet and a main pump state signal; the core cooling state identification module is used for receiving the supercooling degree signal and identifying a temperature interval in which the supercooling degree signal is positioned; the pressure vessel water level prediction module is used for calculating, according to the main pump state signal and the temperature interval in which the supercooling degree signal is positioned, to obtain the water level of the pressure vessel. The device and the method which are provided by the invention implement continuous monitoring on the water level of the pressure vessel by predicting the water level of the pressure vessel, and provide a means for an operator to correctly judge a deterioration degree of a pressure vessel water device; meanwhile, the invention discloses judgment on a deterioration degree of a fuel cladding temperature according to the water level of the pressure vessel, so that the defect of not directly measuring the fuel cladding temperature is overcome, and the basis is provided for the operator to correctly judge a core cooling state so as to adopt effective mitigation measures.

Description

technical field [0001] The invention relates to the technical field of nuclear safety, in particular to a method and a device for predicting the water level of a pressure vessel according to the subcooling degree of the core outlet coolant for a pressurized water reactor nuclear power plant. Background technique [0002] Pressurized water reactor nuclear power plants generally use the water level instrument of the pressurizer to detect the water content of the primary circuit. In practical applications, if the coolant in the pressure vessel is two-phase vapor-liquid, the water level of the pressurizer cannot truly reflect the actual water level of the primary circuit. Wrong water loading information may cause the operator to misdiagnose the cooling state of the core, which will affect the accident handling process and make the accident worsen. [0003] At present, the water level monitoring instruments of pressure vessels are mainly divided into the following types according...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/035
CPCG21C17/035Y02E30/30
Inventor 王振营孙晨李闰生许胜马廷伟刘洪贞
Owner 中广核工程有限公司
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