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Breach Simulation System with Function of Measuring Two-Phase Discharge Flow and Its Measurement Method

A technology for simulating systems and breaches, which is applied in the field of two-phase critical flow experiment research, can solve problems such as easy overflow, large liquid phase flow rate, and high heat capacity of two-phase fluid, so as to avoid inaccurate measurement, reduce system error, and improve operability effect

Active Publication Date: 2016-09-07
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

If conventional single-phase fluid flow measurement instruments are used, such as Venturi flowmeters, vortex flowmeters, etc., since their measurement principles are based on single-phase fluids, it is difficult to give accurate flow values ​​of vapor-liquid two-phase flow
If the conventional weighing method is used, only the total flow rate of the vapor-liquid two-phase can be given, and because the two-phase fluid discharged through the breach has a high heat capacity and contains a large amount of water vapor, especially for the discharge through a large breach, when When the sprayed fluid enters the open container used in the weighing method, it may not be cooled in time and a large amount of steam will be volatilized into the atmosphere, which will affect the accuracy of critical flow measurement
In the prior art, there is a method for separating the two-phase flow into measurable single-phase water and single-phase gas / vapor by using a steam-water separator. Measure single-phase gas / steam flow, but in this method, quartz glass is difficult to withstand the thermal shock of the two-phase critical flow discharge fluid in the loss of water accident, and at the same time, the temperature and density of the liquid phase in the discharge fluid may change with time under the action of the safety system. Changes occur, the quartz glass only measures the volume flow of the liquid phase and cannot give the mass flow, and the scale of the quartz glass is manually read, it is difficult to give an accurate instantaneous flow change value
In addition, for the critical flow sprayed by a large breach, the liquid phase flow rate is relatively large, and it is easy to exceed the range of ordinary measuring containers or measuring devices, making it impossible to measure. If the measured liquid phase fluid is discharged from the container or device when the measurement is stopped midway, Since the sprayed liquid-phase fluid has been entering the measuring container or device, it is not only difficult to completely discharge the measured liquid-phase fluid in the container or device, but also the effective test data of a large time range will be lost in the experiment

Method used

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  • Breach Simulation System with Function of Measuring Two-Phase Discharge Flow and Its Measurement Method

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0035] Such as figure 1 As shown, the breach simulation system with the function of measuring the two-phase discharge flow rate includes a breach discharge simulation pipeline, a steam-water separator 5, a steam measurement pipeline, and a weighing measurement pipeline. The steam-water separator 5 is provided with There are two-phase flow inlets, steam outlets and liquid-phase outlets, wherein: the breach spray simulation pipeline is connected upstream to the breach of the high-temperature, high-pressure thermal-hydraulic circuit, and downstream is connected to the two-phase flow inlet. The aforementioned high-temperature, high-pressure thermal-hydraulic circuit Refers to the thermal-hydraulic circuit of high-temperature and high-pressure fluid, which is the primary reactor circuit in the nuclear reactor system, and the breach of the high-temperature, high-pressure thermal-hydraulic circuit is the breach in the reactor primary circuit 1; A breach in the thermal circuit; the up...

Embodiment 2

[0037] On the basis of Embodiment 1, in this embodiment, the above-mentioned breach spraying simulation pipeline is provided with a size head 2, a breach simulation part 3, and a pneumatic quick-opening ball valve 4 in sequence, and these components are connected by large-diameter stainless steel pipes , the downstream of the pneumatic quick-opening ball valve 4 is connected to the two-phase inflow inlet of the steam-water separator 5, wherein the big and small heads 2 are gradually enlarged small heads, the big mouth end is connected to the breach simulation piece downstream, and the small mouth end is connected to the breach position of the high temperature and high pressure thermal hydraulic circuit, The inner diameter of the large mouth end is 4 to 5 times of the inner diameter of the small mouth end, and the diverging angle is optimized to be 8°-12°, so that the sum of the shape resistance pressure drop and the friction resistance pressure drop of the small head 2 is the mi...

Embodiment 3

[0040]On the basis of Embodiment 1 or 2, in this embodiment, the steam-water separator 5 is a rotary vane-type steam-water separator, and its two-phase inflow inlet and liquid-phase outlet are arranged at the bottom, and the steam outlet is arranged at the top, and the steam-water separator A safety interface is also provided on the 5, and a safety valve 8 is also connected to the safety interface. The two-phase critical flow of steam and water in the simulation pipeline of breach spraying enters the steam-water separator 5 through the two-phase inlet at the bottom. Entering the steam measuring pipeline, the single-phase saturated water is collected by the water guide groove and enters the weighing measuring pipeline.

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Abstract

The invention discloses a crevasse simulation system with a two-phase discharge flow measurement function and a measurement method thereof. The crevasse simulation system comprises a crevasse discharge simulation pipeline, a steam-water separator, a steam measurement pipeline and a weighing measurement pipeline, and the steam-water separator is provided with a two-phase inflow hole, a steam outlet and a liquid phase outlet; the upstream of the crevasse discharge simulation pipeline is connected with a crevasse of a high-temperature high-pressure thermal hydraulic loop, and the downstream is connected with the two-phase inflow hole; the upstream of the steam measurement pipeline is connected with the steam outlet; the upstream of the weighing measurement pipeline is connected with the liquid phase outlet of the steam-water separator. The crevasse simulation system with the two-phase discharge flow measurement function uses the steam-water separator to separate two-phase critical flow into single-phase saturated steam and single-phase saturated water and combines a steam flow meter with a weighing method to measure the crevasse discharge two-phase critical flow, and the problem that the critical flow discharged from a high-temperature high-pressure fluid crevasse is difficult to measure is solved; by means of the crevasse discharge simulation pipeline, the crevasse simulation piece, crevasse control valve and crevasse measurement system arrangement problem is solved.

Description

technical field [0001] The invention relates to the field of experimental research on two-phase critical flow, in particular to a breach simulation system capable of measuring two-phase discharge flow and a measurement method thereof. Background technique [0002] In the field of nuclear technology, the breach loss of water accident is one of the reactor accidents with a relatively high probability of occurrence. Two-phase critical flow during loss of water accident is of great significance to reactor safety. This is because the critical flow rate of the breach determines the loss rate of the core coolant and the pressure relief rate of the primary circuit system. Its size not only directly affects the cooling capacity of the core, but also determines the actions of various safety and emergency systems. time. So far, some experimental studies on two-phase critical flow have been carried out internationally, and various physical models (such as the Henry-Fauske non-equilibr...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00
CPCG21C17/00Y02E30/30
Inventor 曾小康昝元峰周慧辉张妍闫晓
Owner NUCLEAR POWER INSTITUTE OF CHINA