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A Method for Determining the Vapor-Water Interface

A kind of interface, soda water technology, applied in the field of nuclear reactor, to achieve the effect of improving feedback response speed, reducing risk, and fast target value

Active Publication Date: 2016-08-31
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, the existing technology cannot quickly and accurately determine the steam-water separation interface, so it is urgent to adopt a new method to determine the steam-water separation interface to meet the increasingly high safety requirements of nuclear power plants

Method used

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Examples

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Embodiment Construction

[0023] A method for determining the vapor-water interface of the present invention comprises the following steps:

[0024] Step 1. Collect the effective relative pressure P of the primary circuit of the reactor RCS , The absolute pressure of the reactor containment atmosphere P ATM and the temperature T of the characteristic point in the pressure vessel;

[0025] Specifically, the signal source for collecting the relative pressure may be the pressure of the main pipeline of the primary circuit, or the pressure of the voltage stabilizer, or a combination of the two. However, it is necessary to consider the validity of the pressure signal and use the single failure criterion to ensure that the original input of the calculation process is valid in the case of accidents and post-accidents. This requires the selection of relative pressure signals from different locations and the use of calibration calculations Obtain the effective relative pressure P of the primary circuit that c...

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Abstract

The invention belongs to the field of nuclear reactors and in particular relates to a method for determining a vapor-water interface. The method comprises the following steps: 1, collecting effective relative pressure PRCS of a loop of a reactor, reactor containment barometric absolute pressure PATM and temperature T of feature points in a pressure vessel; 2, acquiring absolute pressure PABS of a loop; 3, acquiring a saturation temperature TSAT of a loop coolant; 4, acquiring supercooling degree or superheat degree of the feature points in the pressure vessel; and 5, determining the coolant phase of the feature points in the pressure vessel. Excessive equipment is not needed to be increased, the vapor-water separation interface can be accurately determined, the feedback response speed is improved, the target value can be rapidly determined, and the risk is reduced.

Description

technical field [0001] The invention belongs to the field of nuclear reactors, and in particular relates to a method for determining the steam-water interface by utilizing the supercooling margin. Background technique [0002] In nuclear power plants, the water level of pressure vessels is mainly measured by differential pressure instruments or detectors based on the principle of thermal diffusion. For the differential pressure instrument, because the lower pressure tap needs to open a hole from the bottom of the pressure vessel, which increases the probability of failure of the pressure vessel, so in the pursuit of higher safety in advanced light water reactors, this instrument cannot perform measurement The effect of the water level of the pressure vessel. In response to this situation, there is a water level detector based on the principle of thermal diffusion. This detector adopts the structure of an electric heater and a temperature sensitive element, and determines th...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/035G21C17/022
CPCY02E30/30
Inventor 何鹏何正熙余俊辉李小芬苟拓王华金李红霞陈静霍雨佳朱加良
Owner NUCLEAR POWER INSTITUTE OF CHINA