CN113654760A - Experimental device and experimental method for injection process of steam generator heat transfer tube rupture accident - Google Patents

Experimental device and experimental method for injection process of steam generator heat transfer tube rupture accident Download PDF

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CN113654760A
CN113654760A CN202110992355.3A CN202110992355A CN113654760A CN 113654760 A CN113654760 A CN 113654760A CN 202110992355 A CN202110992355 A CN 202110992355A CN 113654760 A CN113654760 A CN 113654760A
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reaction vessel
heat transfer
steam generator
transfer tube
glass
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张大林
张衍
王成龙
田文喜
苏光辉
秋穗正
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Xian Jiaotong University
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Abstract

本发明公开了蒸汽发生器传热管破裂事故注射过程实验装置及实验方法,该装置包括高压过冷水入口、铅水反应容器、可视化视窗和爆破喷放阀;可视化视窗布置于反应容器两侧,一侧用于观察汽液流动特性,一侧用于红外温度场测量;爆破喷放阀可实现给定压力下阀门的爆破开启;本发明可用于铅铋反应堆蒸汽发生器传热管破裂事故中高压过冷水注入高温铅铋合金过程的实验研究,获得事故中关键两相参数和模型,有助于推动铅铋反应堆加速实现工业化,具有广泛应用前景。

Figure 202110992355

The invention discloses an experimental device and an experimental method for the injection process of steam generator heat transfer tube rupture accident. One side is used to observe the vapor-liquid flow characteristics, and the other side is used to measure the infrared temperature field; the blasting and discharging valve can realize the blasting opening of the valve under a given pressure; the invention can be used in the rupture accident of the heat transfer tube of the steam generator of the lead-bismuth reactor The experimental research on the process of injecting high-temperature lead-bismuth alloys with high-pressure supercooled water has obtained the key two-phase parameters and models in the accident, which will help to accelerate the industrialization of lead-bismuth reactors, and has broad application prospects.

Figure 202110992355

Description

Steam generator heat transfer pipe rupture accident injection process experimental device and experimental method
Technical Field
The invention relates to the field of lead-bismuth reactors, in particular to an experimental device and an experimental method for an injection process of a steam generator heat transfer pipe rupture accident.
Background
The lead bismuth reactor mostly adopts a spiral tube type steam generator, and because of the corrosion characteristic of lead bismuth alloy, the heat transfer tube of the steam generator is easier to have rupture accidents. When a steam generator heat transfer pipe rupture accident occurs, high-pressure supercooled secondary side water can be injected into a primary side high-temperature low-pressure lead bismuth coolant, flash evaporation and steam explosion occur in lead bismuth, steam generated by explosion forms pressure waves to diffuse outwards, chain rupture of other heat transfer pipes can be possibly caused, and a serious accident is caused.
The steam generator heat transfer pipe rupture accident phenomenon is complicated, and research is mainly focused on an experimental method at present, and less attention is paid to program simulation. In order to realize the fine modeling of the process, the interaction between each phase in a lead-water two-phase or lead-water-vapor three-phase system needs to be studied deeply, and due to the opacity and high melting point of the lead-bismuth alloy, a visual experiment is difficult to realize.
Disclosure of Invention
In order to solve the problems existing in the prior art, the invention aims to provide an experimental device and an experimental method for an injection process of a steam generator heat transfer pipe rupture accident, which are used for the visual research of the injection process of injecting supercooled water into high-temperature lead-bismuth alloy in the process, acquiring key parameters in the accident process and establishing a related gas-liquid two-phase action mechanism model.
In order to achieve the purpose, the invention adopts the following technical scheme:
the steam generator heat transfer pipe rupture accident injection process experimental device comprises a supercooled water inlet 1, an inlet pipeline 2, a blasting blow-off valve 4, a visual window 5, a reaction vessel 6 and a reaction vessel outlet 7; the inlet pipeline 2 penetrates through the bottom surface of the reaction vessel 6, the lower end of the inlet pipeline is connected with the supercooled water inlet 1, the upper end of the inlet pipeline is connected with the blasting blow-off valve 4, and the inlet pipeline 2 and the bottom surface of the reaction vessel 6 are integrally processed; the supercooled water inlet 1 is connected with an external high-pressure supercooled water source; the visual window 5 comprises two pieces of glass which are respectively arranged at two sides of the reaction vessel 6 and are compressed and sealed with the reaction vessel through a sealing flange 3, and a high-speed camera 503 and an infrared thermometer 504 which are respectively arranged at the same height outside the two pieces of glass are respectively used for gas-liquid two-phase flow characteristic observation and temperature field measurement in the experiment process; or the visual window 5 comprises a piece of glass, is arranged on one side of the reaction vessel 6, and measures the temperature field by arranging a thermocouple on the back plate of the reaction vessel; and electric tracing heat is uniformly distributed in the area outside the visible window outside the reaction vessel 6 and is used as a heat source for melting the lead-bismuth alloy.
The reaction container 6 is made of anti-corrosion austenitic stainless steel, is in a sliced shape, and is convenient for observing the flow characteristics of the lead and the water.
The visual window 5 comprises a piece of round special glass 501 and a piece of round germanium glass 502, a high-speed camera 503 is arranged at the same height outside the special glass 501 and used for observing the gas-liquid two-phase flow characteristics in the experiment process, and an infrared thermometer 504 is arranged at the same height outside the germanium glass 502 and used for measuring the temperature field in the experiment process.
The special glass 501 is made of a heat-resistant pressure-bearing material (such as high borosilicate glass).
The 4 bodies of blasting blow-off valve are brass, and valve body 402 is connected with inlet pipe 2 through screw thread 401, adopts the high accuracy lathe to draw on the valve body top face and has the mar 403 that the degree of depth is different, can realize the blasting of valve under the different upstream pressure and open through control mar degree of depth.
An experimental method for an injection process of a steam generator heat transfer pipe rupture accident is characterized in that after a supercooled water inlet 1 is connected with a high-pressure supercooled water source, firstly, the water source is started to inject supercooled water, so that cold water is filled in an inlet pipeline 2 and is in contact with a blasting blow-off valve 4, then, the pressure is gradually increased to an experimental design pressure, the blasting blow-off valve 4 is broken, and an experiment is started; measuring the flow characteristics of steam-water phases in the experimental section by a high-speed camera, and measuring the temperature field distribution in the experimental section by an infrared thermometer; after the experiment is finished, steam in the experimental device is discharged through the outlet 7 of the reaction container, and the residual lead-bismuth alloy in the reaction container 6 is cooled for the next use.
The method can be used for experimental research on the process of injecting high-pressure supercooled water into high-temperature lead-bismuth alloy in the cracking accident of the heat transfer pipe of the steam generator of the lead-bismuth reactor, and key two-phase parameters and models in the accident are obtained.
Drawings
Fig. 1 is a front view of the overall structure of the present invention.
Fig. 2 is a side view of the overall structure of the present invention.
Fig. 3 is a schematic structural view of the burst disk valve 4.
Fig. 4 is an extended embodiment of the present invention.
Detailed Description
The invention is described in further detail below with reference to the figures and specific examples.
Example 1 was carried out:
as shown in fig. 1 and 2, the experimental device for the steam generator heat transfer tube rupture accident injection process comprises a supercooled water inlet 1, an inlet pipeline 2, a blasting blow-off valve 4, a visualization window 5, a reaction vessel 6 and a reaction vessel outlet 7; the inlet pipeline 2 penetrates through the bottom surface of the reaction vessel 6, the lower end of the inlet pipeline is connected with the supercooled water inlet 1, the upper end of the inlet pipeline is connected with the blasting blow-off valve 4, and the inlet pipeline 2 and the bottom surface of the reaction vessel 6 are integrally processed; the supercooled water inlet 1 is connected with an external high-pressure supercooled water source; the visual window 5 comprises two pieces of glass which are respectively arranged at two sides of the reaction vessel 6 and are compressed and sealed with the reaction vessel through a sealing flange 3, and a high-speed camera 503 and an infrared thermometer 504 which are respectively arranged at the same height outside the two pieces of glass are respectively used for gas-liquid two-phase flow characteristic observation and temperature field measurement in the experiment process; and electric tracing heat is uniformly distributed in the area outside the visible window outside the reaction vessel 6 and is used as a heat source for melting the lead-bismuth alloy.
In this example, the reaction vessel 6 is made of corrosion-resistant austenitic stainless steel and is in the shape of a sliced piece, so that the flow characteristics of the lead and water phases can be observed conveniently.
The visual window 5 comprises a piece of round special glass 501 (high borosilicate glass) and a piece of round germanium glass 502, a high-speed camera 503 is arranged at the same height outside the special glass 501 and used for observing the gas-liquid two-phase flow characteristics in the experiment process, and an infrared thermometer 504 is arranged at the same height outside the germanium glass 502 and used for measuring the temperature field in the experiment process.
In this example, the reaction vessel 6 is made of 316L stainless steel, has dimensions of 400mm by 500mm by 10mm and a diameter of the visualization window of 300mm, and is mounted at a height of 200mm from the bottom surface of the reaction vessel 6. The special glass used in this example can withstand a pressure of 3MPa and a temperature of 300 ℃.
As shown in fig. 3, the body of the blasting blow-off valve 4 is made of brass, the valve body 402 is connected with the inlet pipeline 2 through threads 401, scratches 403 with different depths are scribed on the top surface of the valve body by a high-precision lathe, and blasting opening of the valve under different upstream pressures can be realized by controlling the depths of the scratches.
An experimental method for an injection process of a steam generator heat transfer pipe rupture accident is characterized in that after a supercooled water inlet 1 is connected with a high-pressure supercooled water source, firstly, the water source is started to inject supercooled water, so that cold water is filled in an inlet pipeline 2 and is in contact with a blasting blow-off valve 4, then, the pressure is gradually increased to an experimental design pressure, the blasting blow-off valve 4 is broken, and an experiment is started; measuring the flow characteristics of steam-water phases in the experimental section by a high-speed camera, and measuring the temperature field distribution in the experimental section by an infrared thermometer; after the experiment is finished, steam in the experimental device is discharged through the outlet 7 of the reaction container, and the residual lead-bismuth alloy in the reaction container 6 is cooled for the next use.
In the example, the thickness of the top of the blasting blow-off valve 4 is 3mm, and through multiple experimental tests, the scratch depths of 2.4mm, 1.7mm and 1.2mm can respectively realize blasting opening under the upstream pressures of 1MPa, 2MPa and 3 MPa.
Example 2 was carried out:
as shown in fig. 4, because germanium glass is expensive and has low pressure bearing, it is vulnerable in the experiment, and for the economic consideration of the experiment, the invention provides an extended embodiment, i.e. germanium glass and infrared temperature field measurement are eliminated, and the temperature field measurement is performed by arranging a thermocouple on the back plate of the reaction vessel. Because the reaction vessel of the invention adopts a slice type design, the distance between the front and the back of the reaction vessel 6 is very small, so the temperature change in the transverse direction is small, the temperature of the thermocouple arranged on the back plate of the reaction vessel can be regarded as the fluid temperature, and meanwhile, the thermocouple arranged on the back plate of the reaction vessel can reduce the disturbance to the flow. The rest of the arrangement is the same as in embodiment example 1.
The foregoing is illustrative of the present invention only and is not to be construed as limiting thereof, and variations and modifications to the above-described embodiments, within the true spirit and scope of the invention, should be considered as within the scope of the claims of the present invention to those skilled in the art.

Claims (6)

1.蒸汽发生器传热管破裂事故注射过程实验装置,其特征在于:包括过冷水入口(1)、入口管道(2)、爆破喷放阀(4)、可视化视窗(5)、反应容器(6)和反应容器出口(7);所述入口管道(2)贯穿反应容器(6)底面,下端连接过冷水入口(1),上端连接爆破喷放阀(4),所述入口管道(2)与反应容器(6)底面为一体加工而成;所述过冷水入口(1)与外界高压过冷水源连接;所述可视化视窗(5)包括两块玻璃,分别布置于反应容器(6)两侧,与反应容器之间通过密封法兰(3)压紧密封,两块玻璃外同一高度分别布置有高速摄像仪(503)和红外测温仪(504),分别用于实验过程中气液两相流动特性观测和温度场测量;或可视化视窗(5)包括一块玻璃,布置于反应容器(6)一侧,采用在反应容器背板上布置热电偶的方式进行温度场测量;所述反应容器(6)外部除可视化视窗外的区域均布置有电伴热,作为铅铋合金熔化的热源。1. The steam generator heat transfer tube rupture accident injection process experimental device is characterized in that: it comprises a supercooled water inlet (1), an inlet pipeline (2), a blasting discharge valve (4), a visual window (5), a reaction vessel ( 6) and the reaction vessel outlet (7); the inlet pipe (2) runs through the bottom surface of the reaction vessel (6), the lower end is connected to the supercooled water inlet (1), the upper end is connected to the blasting and discharge valve (4), and the inlet pipe (2) ) is integrally processed with the bottom surface of the reaction vessel (6); the supercooled water inlet (1) is connected with an external high-pressure supercooled water source; the visual window (5) includes two pieces of glass, which are respectively arranged in the reaction vessel (6) The two sides are pressed and sealed with the reaction vessel by the sealing flange (3), and a high-speed camera (503) and an infrared thermometer (504) are respectively arranged at the same height outside the two pieces of glass, which are respectively used for gas during the experiment. Liquid two-phase flow characteristic observation and temperature field measurement; or the visualization window (5) includes a piece of glass, which is arranged on one side of the reaction vessel (6), and the temperature field measurement is performed by arranging a thermocouple on the back plate of the reaction vessel; the Electric heat tracing is arranged on the outside of the reaction vessel (6) except for the visualization window, as a heat source for the melting of the lead-bismuth alloy. 2.根据权利要求1所述的蒸汽发生器传热管破裂事故注射过程实验装置,其特征在于:所述反应容器(6)为防腐蚀奥氏体不锈钢制成,形状为切片型,便于观察铅水两相流动特性。2. steam generator heat transfer tube rupture accident injection process experimental device according to claim 1, is characterized in that: described reaction vessel (6) is made of anti-corrosion austenitic stainless steel, and the shape is slice type, easy to observe Lead-water two-phase flow characteristics. 3.根据权利要求1所述的蒸汽发生器传热管破裂事故注射过程实验装置,其特征在于:所述可视化视窗(5)包括一块圆形特种玻璃(501)和一块圆形锗玻璃(502),,特种玻璃(501)外同一高度布置有高速摄像仪(503),锗玻璃(502)外部同一高度处布置有红外测温仪(504)。3. The steam generator heat transfer tube rupture accident injection process experimental device according to claim 1, wherein the visual window (5) comprises a circular special glass (501) and a circular germanium glass (502) ), a high-speed camera (503) is arranged at the same height outside the special glass (501), and an infrared thermometer (504) is arranged at the same height outside the germanium glass (502). 4.根据权利要求3所述的蒸汽发生器传热管破裂事故注射过程实验装置,其特征在于:所述特种玻璃(501)的材质为耐热承压玻璃材料。4 . The experimental device for the injection process of steam generator heat transfer tube rupture accident according to claim 3 , wherein the material of the special glass ( 501 ) is a heat-resistant pressure-bearing glass material. 5 . 5.根据权利要求1所述的蒸汽发生器传热管破裂事故注射过程实验装置,其特征在于:所述爆破喷放阀(4)本体为黄铜制作,阀体(402)与入口管道(2)之间通过螺纹(401)连接,阀体顶部面上采用高精度车床划有深度不同的划痕(403),通过控制划痕深度实现不同上游压力下阀门的爆破开启。5. The steam generator heat transfer tube rupture accident injection process experimental device according to claim 1, is characterized in that: the body of the blasting and blowing valve (4) is made of brass, and the valve body (402) and the inlet pipe (402) are made of brass. 2) They are connected by threads (401), and the top surface of the valve body is marked with scratches (403) of different depths by using a high-precision lathe. By controlling the depth of the scratches, the valve can be opened by blasting under different upstream pressures. 6.权利要求1至5任一项所述的蒸汽发生器传热管破裂事故注射过程实验装置的实验方法,其特征在于:过冷水入口(1)连接高压过冷水源后,首先开启水源将过冷水注入,使冷水充满入口管道(2),与爆破喷放阀(4)接触,然后逐渐加压至实验设计压力,冲破爆破喷放阀(4),开始实验;通过高速摄像仪(503)测量实验段中蒸汽-水两相流动特性,通过红外测温仪(504)测量实验段中温度场分布;实验结束后,通过反应容器出口(7)排出实验装置中蒸汽,将反应容器(6)中剩余铅铋合金冷却待下次使用。6. the experimental method of the steam generator heat transfer tube rupture accident injection process experimental device according to any one of claims 1 to 5, it is characterized in that: after the supercooled water inlet (1) is connected to the high pressure supercooled water source, first open the water source to The supercooled water is injected to fill the inlet pipe (2) with cold water, contact with the blasting and discharge valve (4), and then gradually pressurize to the experimental design pressure, burst the blasting and discharge valve (4), and start the experiment; through the high-speed camera (503 ) measure the steam-water two-phase flow characteristic in the experimental section, measure the temperature field distribution in the experimental section by infrared thermometer (504); 6) The remaining lead-bismuth alloy is cooled for next use.
CN202110992355.3A 2021-08-27 2021-08-27 Experimental device and experimental method for injection process of steam generator heat transfer tube rupture accident Pending CN113654760A (en)

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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114758801A (en) * 2022-02-24 2022-07-15 上海交通大学 Experimental device and experimental method for rupture of heat transfer tube of steam generator
CN114974627A (en) * 2022-05-30 2022-08-30 西北核技术研究所 An experimental system and method for measuring the diving depth of water vapor in lead-bismuth alloys
CN115132385A (en) * 2022-07-01 2022-09-30 西安交通大学 Experimental system and method for interaction of molten lead-based reactor core and coolant

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108597625A (en) * 2018-05-08 2018-09-28 西安交通大学 A kind of experimental provision for studying fusant migratory behaviour in lead base reactor cluster channel
CN110553974A (en) * 2019-08-16 2019-12-10 西安交通大学 System and method for testing ultrahigh-temperature corrosion of structural material under severe accident of nuclear reactor
CN111276268A (en) * 2020-02-28 2020-06-12 西安交通大学 Experimental device and method for researching thermal hydraulic characteristics of lead-based stack evaporator heat transfer pipe rupture accident
CN111781075A (en) * 2020-07-10 2020-10-16 西安交通大学 Experimental device and method for rupture mechanical impact and bubble migration of heat transfer tube of lead-based reactor evaporator

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108597625A (en) * 2018-05-08 2018-09-28 西安交通大学 A kind of experimental provision for studying fusant migratory behaviour in lead base reactor cluster channel
CN110553974A (en) * 2019-08-16 2019-12-10 西安交通大学 System and method for testing ultrahigh-temperature corrosion of structural material under severe accident of nuclear reactor
CN111276268A (en) * 2020-02-28 2020-06-12 西安交通大学 Experimental device and method for researching thermal hydraulic characteristics of lead-based stack evaporator heat transfer pipe rupture accident
CN111781075A (en) * 2020-07-10 2020-10-16 西安交通大学 Experimental device and method for rupture mechanical impact and bubble migration of heat transfer tube of lead-based reactor evaporator

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114758801A (en) * 2022-02-24 2022-07-15 上海交通大学 Experimental device and experimental method for rupture of heat transfer tube of steam generator
CN114974627A (en) * 2022-05-30 2022-08-30 西北核技术研究所 An experimental system and method for measuring the diving depth of water vapor in lead-bismuth alloys
CN115132385A (en) * 2022-07-01 2022-09-30 西安交通大学 Experimental system and method for interaction of molten lead-based reactor core and coolant
CN115132385B (en) * 2022-07-01 2023-08-22 西安交通大学 Experimental system and method for interaction between core melt and coolant in lead-based reactor

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