Heat exchanger rupture simulation system and method for fusion reactor helium-cooled blanket cooling system

Abstract

The present invention relates to a heat exchanger rupture experimental system and method for a fusion reactor helium-cooled blanket cooling system. The heat exchanger rupture experimental system for a fusion reactor helium-cooled blanket cooling system comprises: a first circuit for conveying helium; a second circuit for conveying water; a simulated rupture pipe, one end of which is connected to the first circuit and the other end of which is connected to the second circuit, and a valve is provided on the simulated rupture pipe; and a steam-water collection device, which is provided on the helium conveying pipe. By providing the heat exchanger rupture experimental system for a fusion reactor helium-cooled blanket cooling system, the effects of a heat exchanger rupture accident on the pressure and temperature of the secondary water circuit, as well as the mechanism and possible effects of secondary water entering the helium circuit through the rupture, can be conveniently studied through simulated tests.

Description

Technical Field

[0001] The present invention relates to the maintenance of a helium-cooled blanket cooling system for a fusion reactor, and in particular to a heat exchanger rupture simulation component for the helium-cooled blanket cooling system for a fusion reactor, a heat exchanger rupture experimental system for the helium-cooled blanket cooling system for a fusion reactor, and a method for simulating the rupture of a heat exchanger pipe. Background Art

[0002] With humanity's growing demand for energy, the scarcity of limited fossil fuel resources, and increasing attention to environmental quality, we must consider new clean, sustainable, and renewable energy sources. Nuclear fusion energy, considered the cleanest energy source with the greatest development potential due to its abundant nuclear fuel, pollution-free nature, and lack of high-level radioactive waste, is a challenging task. Numerous issues remain, such as steady-state or long-duration pulsed operation of fusion reactors and system safety issues in the event of an accident. To address the safety challenges of fusion reactors during engineering, fusion reactor system safety design and accident analysis are playing an increasingly important role in fusion reactor design and development. With the commencement of engineering design for the International Thermonuclear Experimental Reactor (ITER), fusion research has gradually entered the engineering phase, and safety design and accident analysis have been incorporated into the project design and development process.

[0003] During the initial design phase of a fusion reactor, system safety design and accident analysis are also conducted. In fusion reactor design, accident analysis primarily encompasses two aspects: 1. Verifying each system and safety control function through thermal-hydraulic transient analysis ensures that the consequences of a nuclear accident are controllable and mitigable; 2. Based on calculation results, analyzing design flaws in each system and optimizing them to achieve optimal system economics and safety. The helium-cooled blanket system is a key system for realizing fusion energy applications in a fusion reactor, and accident analysis is essential for ensuring the safe operation of the reactor. After several generations of design updates and accident analysis, the helium-cooled blanket system has significantly improved its thermal and mechanical performance. However, to verify the accuracy of the safety design and accident analysis, design basis accident verification experiments based on the helium-cooled blanket cooling system design in the fusion reactor are required.

[0004] The rupture of the heat exchanger pipe in the helium-cooled blanket cooling system is one of the accidents that must be analyzed for the helium-cooled blanket system, and it is also related to the design of the overall water cooling system of the fusion reactor. After the heat exchanger pipe ruptures, the coolant in the cooling system of the helium-cooled solid experimental blanket module is lost, and the high-pressure helium (above 8MPa) in the helium cooling circuit will enter the low-pressure water cooling system (0.8MPa). Accident experiments are needed to study the impact of the heat exchanger rupture accident on the pressure and temperature of the secondary water circuit, as well as the mechanism and possible impact of the secondary water entering the helium circuit through the rupture. The experimental measurement method and experimental section design for the helium gas spray and secondary water backflow into the helium cooling system in the event of a helium working medium heat exchanger pipe rupture accident are still lacking. Summary of the Invention

[0005] The problem to be solved by the present invention is to provide a heat exchanger rupture simulation system and method for a fusion reactor helium-cooled blanket cooling system that is suitable for the design characteristics of the helium-cooled system when experimentally verifying a heat exchanger rupture accident in the fusion reactor helium-cooled blanket cooling system. The system can be used to test the helium gas spraying process to the water side after the heat exchanger rupture accident and the backflow rate of water into the helium pipeline after the accident, so as to facilitate the study of the impact of the heat exchanger rupture accident on the pressure and temperature of the secondary side water circuit, as well as the mechanism and possible impact of the secondary side water entering the helium circuit through the rupture.

[0006] A first aspect of the present invention provides a heat exchanger rupture simulation component for a helium-cooled blanket cooling system of a fusion reactor, comprising: a simulated rupture pipe, one end of the simulated rupture pipe being used to communicate with a helium delivery pipeline, and the other end being used to communicate with a secondary-side water delivery pipeline, the simulated rupture pipe being provided with a valve for controlling the opening and closing of the simulated rupture pipe; and a steam-water collecting device, the steam-water collecting device being used to be arranged on the helium delivery pipeline, and the arrangement position being located downstream of the connection between the simulated rupture pipe and the helium delivery pipeline; the steam-water collecting device comprising: a curved pipe, the curved pipe being arranged on the helium delivery pipeline as a bypass, the inlet and outlet of the curved pipe being provided with valves, at least a portion of the curved pipe being bent downward in the direction of gravity, and a sampling pipe for draining the liquid in the pipe being connected to the lower part of the curved portion; a first water tank, the spiral pipe being arranged in the first water tank; a first isolation valve, the first isolation valve being used to be arranged on the helium delivery pipeline, the two ends of the spiral pipe connected to the helium delivery pipeline being respectively located at the front and rear ends of the first isolation valve. Multiple simulated breach pipes of varying diameters, or at least sections of varying diameters, can be placed between the helium and secondary water delivery lines to simulate breaches of varying sizes. This not only improves safety, allowing experiments to be conducted in a safer environment and avoiding the risk of direct high-pressure gas leakage, but also allows for the study of the effects of breaches of varying sizes on gas flow characteristics. Multiple experiments can be conducted to provide a reference for breach management in practical scenarios. Furthermore, using pipelines for breach simulation reduces experimental costs, avoiding the expense of manufacturing experimental equipment for breaches of varying sizes.

[0007] By using this heat exchanger breach simulation assembly for a fusion reactor helium-cooled blanket cooling system, an experimental system for detecting water backflow into the helium cooling system is formed, realizing a method for testing the quality of backflowed steam and water. In this heat exchanger breach simulation assembly, the simulated breach pipe can be placed between the helium delivery pipeline and the secondary water delivery pipeline to simulate a breach accident in the heat exchanger between the two systems. The steam and water collection device is placed on the helium delivery pipeline to condense the steam and water in the secondary water delivery pipeline through the spiral pipe after the water in the pipeline flows into the helium delivery pipeline due to the pressure difference. This facilitates the statistical analysis of the water quality entering the helium system during the accident experiment.

[0008] In order to study the impact of a heat exchanger rupture accident on the pressure and temperature of the secondary water circuit, as well as the mechanism and possible impact of secondary water entering the helium circuit through the rupture, the present invention uses a heat exchanger rupture simulation component for a fusion reactor helium-cooled blanket cooling system to reflect the impact of a rupture accident on the pressure and temperature of the external environment.

[0009] In some feasible embodiments, the curved tube is a transversely arranged spiral tube, with the sampling tube disposed at the bottom of the spiral tube in the direction of gravity for discharging the cooled water. The upper end of the sampling tube is connected to the bottom of the spiral tube, and the lower end extends out of the first water tank, thereby discharging the cooled water to a designated location for measurement. This sampling tube is also equipped with a valve.

[0010] In some feasible embodiments, the steam-water collection device further includes an online steam-water sensor disposed within the spiral tube for online monitoring of the steam-water content in the sampled gas. The online steam-water sensor is communicatively connected to an online steam-water detection device to transmit collected steam-water signals to the online steam-water detection device.

[0011] The second aspect of the present invention provides a heat exchanger rupture experimental system for a helium-cooled blanket cooling system of a fusion reactor, comprising: a first circuit, the first circuit comprising a pipeline for conveying helium; a second circuit, the second circuit comprising a pipeline for conveying water; a simulated rupture pipeline, one end of the simulated rupture pipeline being connected to the first circuit and the other end being connected to the second circuit, the simulated rupture pipeline being provided with a valve for controlling the opening and closing of the simulated rupture pipeline; a steam-water collecting device, the steam-water collecting device being provided on the helium conveying pipeline; a plurality of the simulated rupture pipelines being arranged, and among the plurality of simulated rupture pipelines, each or some of the simulated rupture pipelines has a different or Some sections have different diameters; the steam-water collection device is located downstream of the connection between the simulated breached pipe and the first circuit; the steam-water collection device includes: a curved pipe, installed as a bypass on the helium delivery pipeline, with valves installed at its inlet and outlet. At least a portion of the curved pipe bends downward in the direction of gravity, with a sampling tube connected to the lower portion of the curved portion for draining the liquid within the pipe; a first water tank, within which the spiral pipe is located; and a first isolation valve, installed on the helium delivery pipeline, with the ends of the spiral pipe connecting to the helium delivery pipeline located at the front and rear ends of the first isolation valve, respectively. The aforementioned first circuit can serve as a simulated helium cooling system or as part of a simulated helium cooling system.

[0012] The second circuit simulates the secondary side water delivery system.

[0013] By setting up the above-mentioned heat exchanger rupture experimental system for the fusion reactor helium-cooled blanket cooling system, it is possible to conveniently study the impact of a heat exchanger rupture accident on the pressure and temperature of the secondary water circuit, as well as the mechanism and possible impact of the secondary water entering the helium circuit through the rupture through simulation experiments.

[0014] In some feasible embodiments, the first circuit includes a high-pressure helium gas delivery pipe, the inlet and outlet of which are respectively connected to a Venturi flowmeter; a Venturi flowmeter is provided on the simulated rupture pipe, and the Venturi flowmeter is located upstream of the valve on the simulated rupture pipe.

[0015] In some feasible embodiments, both ends of the inlet and outlet of the curved pipe are connected to the high-pressure helium delivery pipe, and a first isolation valve arranged on the high-pressure helium delivery pipe is provided between the two points where the curved pipe is connected to the high-pressure helium delivery pipe.

[0016] In some feasible embodiments, the curved pipe is a transversely arranged spiral pipe, and the sampling pipe is provided at the bottom of the spiral pipe in the gravity direction for draining out the cooled water.

[0017] In some feasible embodiments, a stop valve is further arranged on the simulated rupture pipe, and a rupture simulation flange is provided on the side of the stop valve close to the second circuit along the direction of helium flow to the second circuit; among multiple simulated rupture pipes, the outlet diameters of the rupture simulation flanges of the simulated rupture pipes on the side close to the second circuit are different.

[0018] In some feasible embodiments, the second circuit includes: a water medium delivery pipeline; a second water tank, both ends of the water medium delivery pipeline are connected to the second water tank; the water medium delivery pipeline is connected to the first circuit through a simulated broken pipe; and a pressure stabilizing tank, which is connected to the second water tank.

[0019] A third aspect of the present invention further provides a method for simulating a heat exchanger pipe rupture, using the heat exchanger rupture experimental system of the fusion reactor helium-cooled blanket cooling system according to the second aspect and its improved solution. The method for simulating a heat exchanger pipe rupture comprises the following steps:

[0020] Close the inlet and outlet valves of the first circuit to simulate triggering a shutdown signal;

[0021] After the helium enters the second circuit from the simulated ruptured pipe;

[0022] When the pressure of the second circuit is higher than the preset pressure test limit of the second circuit or the pressure of the first circuit is lower than the preset pressure test limit of the first circuit, the closing response signal of the inlet and outlet valves of the first circuit is activated;

[0023] The inlet and outlet valves of the first circuit are completely closed according to the predetermined closing time. When the pressure of the first circuit and the second circuit reaches equilibrium and the flow change measured by the flow meter of the simulated ruptured pipe is zero, the experiment ends and the experimental data is collected. At the same time, the valve of the simulated ruptured pipe is closed, and the mass of helium entering the second circuit is measured by detecting the liquid level information in the pressure-surge tank of the second circuit and the pressure and temperature information of the second circuit;

[0024] When the pressure in the second circuit is greater than or equal to the pressure in the first circuit, the first isolation valve on the first circuit is closed, and the second isolation valve, the third isolation valve and the valve on the simulated rupture pipe are opened, so that the water vapor entrained in the helium will enter the spiral tube in the first water tank. The cooling water flowing in the first water tank forcibly cools the spiral tube to condense the steam in the helium into condensed water;

[0025] An online steam-water detection device is used to detect the real-time steam-water content in the helium. After the valve of the simulated ruptured pipeline and the first isolation valve are closed, the spiral tube and the main loop pipeline are cooled to room temperature. At this time, the valve of the sampling tube is opened, and all the water collected in the spiral tube is discharged and weighed to obtain the mass of the water entering the first loop helium system from the second loop during the accident experiment.

[0026] Fusion reactor engineering is currently in the preliminary design stage. Its helium-cooled blanket system is one of the core systems of a fusion reactor. The blanket cooling system design is complex and lacks experimental data to support the consequences of safety accidents. Based on the design of the Chinese helium-cooled blanket system of the International Thermonuclear Reactor (ITER), this paper uses the existing helium cooling system verification test bench to develop a test bench suitable for the helium cooling system design basis accident (heat exchanger pipe rupture).

[0027] This heat exchanger rupture experimental system for the helium-cooled blanket cooling system of a fusion reactor and the method for simulating the rupture of a heat exchanger pipe can fill the gaps in the design and method of pressure and temperature measurement after a heat exchanger rupture accident in accident experiments of helium-cooled blanket systems in the fusion reactor field, as well as the gaps in the design and method of a test platform for water backflow into the helium cooling loop after an accident. This provides a feasible and efficient system and method for accident safety verification of the helium-cooled blanket system in the engineering design stage of a fusion reactor. BRIEF DESCRIPTION OF THE DRAWINGS

[0028] The drawings described herein are used to provide a further understanding of the embodiments of the present invention, constitute a part of this application, and do not constitute a limitation of the embodiments of the present invention. In the drawings:

[0029] Figure 1 A schematic diagram illustrating a current helium-cooled solid-state experimental blanket module cooling system according to an embodiment;

[0030] Figure 2 Schematic diagram for illustrating the heat exchanger breach simulation assembly for the fusion reactor helium-cooled blanket cooling system in Example 1 and the heat exchanger breach experimental system for the fusion reactor helium-cooled blanket cooling system in Example 2;

[0031] Figure 3 is a schematic diagram for illustrating the steam-water collecting device in Examples 1 and 2;

[0032] Figure 4A schematic diagram for explaining the cleaning of the steam-water collecting device in Examples 1 and 2;

[0033] Figure 5 Schematic diagram of two simulated flanges with different pipe diameters for illustrating the simulated broken pipes in Examples 1 and 2;

[0034] Figure 6 A modeling diagram for illustrating a heat exchanger breach experimental system for a fusion reactor helium-cooled blanket cooling system in Example 2;

[0035] Figure 7 is a modeling diagram for illustrating the steam-water collecting device in Examples 1 and 2;

[0036] Figure 8 A diagram illustrating the end structure of the second water tank and the surge tank body in Example 2;

[0037] Figure 9 A schematic diagram illustrating the working principle of the Venturi flowmeter in Examples 1 and 2;

[0038] Reference numerals and corresponding component names:

[0039] 1-Helium blower, 2-Electric heater, 3-Regenerator, 4-Heat exchanger, 5-Dust collector, 6-Simulated breach pipe, 610-Breakage simulated flange, 620-Second Venturi flowmeter, 630-Pneumatic stop valve, 7-Helium delivery pipeline, 8-Steam-water collection device, 810-Curved pipe, 820-First water tank, 830-First isolation valve, 840-Sampling tube, 850-Second isolation valve, 860-Third isolation valve, 9-Water medium delivery pipeline, 10-Second water tank, 11-Pressure stabilizing tank, 12-First Venturi flowmeter. DETAILED DESCRIPTION

[0040] In order to make the objectives, technical solutions and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with examples and drawings. The exemplary embodiments of the present invention and their descriptions are only used to explain the present invention and are not intended to limit the present invention.

[0041] In the following description, numerous specific details are set forth to provide a thorough understanding of the present invention. However, it will be apparent to one skilled in the art that these specific details are not necessarily required to practice the present invention. In other instances, well-known structures, circuits, materials, or methods are not described in detail to avoid obscuring the present invention.

[0042] Throughout this specification, references to "one embodiment," "an embodiment," "an example," or "an example" mean that a particular feature, structure, or characteristic described in connection with the embodiment or example is included in at least one embodiment of the present invention. Therefore, appearances of the phrases "one embodiment," "an embodiment," "an example," or "an example" in various places throughout this specification are not necessarily all referring to the same embodiment or example. Furthermore, the particular features, structures, or characteristics may be combined in one or more embodiments or examples in any suitable combinations and / or subcombinations. Furthermore, it will be understood by those of ordinary skill in the art that the figures provided herein are for illustrative purposes only and are not necessarily drawn to scale. As used herein, the term "and / or" includes any and all combinations of one or more of the associated listed items.

[0043] In the description of the present invention, it should be understood that the terms "front", "rear", "left", "right", "up", "down", "vertical", "horizontal", "high", "low", "inside", "outside", etc., indicating directions or positional relationships, are based on the directions or positional relationships shown in the accompanying drawings, and are only for the convenience of describing the present invention and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific direction, be constructed and operated in a specific direction, and therefore cannot be understood as limiting the scope of protection of the present invention.

[0044] Reference Figure 1 The main circuit of the helium-cooled solid-state experimental blanket module cooling system is mainly composed of a helium fan 1, an electric heater 2, a regenerator 3, a heat exchanger 4, a dust collector 5, a regulating valve, a safety valve and pipelines. At present, the heat exchanger 4 of the main circuit is designed as a shell and tube heat exchanger.

[0045] In response to the helium release and secondary water backflow into the primary circuit in a heat exchanger pipe rupture accident, in order to study the impact of the heat exchanger rupture accident on the pressure and temperature of the secondary water circuit, as well as the mechanism and possible impact of secondary water entering the helium circuit through the rupture, this embodiment designs simulated rupture pipes 6 with different rupture sizes to reflect the impact of different rupture sizes on the pressure and temperature of the external environment after the accident.

[0046] Reference Figures 2 to 7, Example 1, a heat exchanger rupture simulation component for a fusion reactor helium-cooled blanket cooling system, comprising: a simulated rupture pipe 6, one end of which is used to communicate with a helium delivery pipeline 7, and the other end is used to communicate with a secondary side water delivery pipeline, and a valve for controlling the opening and closing of the simulated rupture pipe 6 is provided on the simulated rupture pipe 6; and a steam-water collecting device 8, which is used to be arranged on the helium delivery pipeline 7, and is arranged at a position downstream of the connection between the simulated rupture pipe 6 and the helium delivery pipeline 7; the steam-water collecting device 8 comprises: a curved pipe 810, the curved pipe 810 is arranged on the helium delivery pipeline 7 as a bypass, and the inlet and outlet of the curved pipe 810 are equipped with valves. At least a portion of the curved pipe 810 is bent downward along the direction of gravity, and a sampling tube 840 for draining the liquid in the tube is connected to the lower part of the bent portion; a first water tank 820, the spiral tube is arranged in the first water tank 820; the first isolation valve 830, the first isolation valve 830 is used to be arranged on the helium delivery pipeline 7, and the two ends of the spiral tube connected to the helium delivery pipeline 7 are respectively located at the front and rear ends of the first isolation valve 830.

[0047] Multiple simulated breach pipes 6 of different diameters or at least sections of different diameters can be provided between the helium delivery pipeline 7 and the secondary water delivery pipeline to simulate breaches of different sizes. Simulated breach pipes 6 can simulate breaches of different sizes by providing breach simulation flanges 610 of different diameters on the side of the valve close to the secondary water delivery pipeline, such as Figure 5 , change the pipe diameter close to the secondary side water delivery pipeline, adjust different simulated ruptures to facilitate replacement and adjustment.

[0048] The heat exchanger rupture simulation component for the fusion reactor helium-cooled blanket cooling system of this embodiment is arranged on the helium delivery pipeline 7 and between the helium delivery pipeline and the secondary side water delivery pipeline to conduct simulation tests to facilitate reflecting the impact of the rupture accident on the pressure and temperature of the external environment.

[0049] The simulated breach pipe 6 is connected with a necked butt-weld flange. That is, the simulated breach pipe 6 can be divided into two sections. The section close to the helium delivery pipeline 7 is a pipeline for arranging various devices, and the other section close to the secondary water delivery pipeline is connected to the aforementioned section via a necked butt-weld flange. The steel pipe size and wall thickness are selected according to "GB17395-2008 Seamless Steel Pipe Dimensions, Shape, Weight and Permissible Deviations". According to the calculation of the minimum wall thickness of straight pipes subjected to internal pressure in 6.3.2.1 of "GB / T32270-2015 Pressure Piping Specification Power Pipes" and the description of the allowable stress of high-alloy steel pipes in "GB 150.2-2011", the wall thickness formula (1) is determined according to the inner diameter of the pipe as follows:

[0050]

[0051] Substitute the allowable stress into the above formula and, based on the calculation results, look up the table to select the experimental section pipe material with a wall thickness that can meet the design pressure and design temperature conditions.

[0052] A certain length of straight pipe section with a rupture is selected as the model of the simulated rupture experimental section. According to the actual needs, 5 rupture sizes are selected from the simulated rupture size range to design the accident rupture. A round pipe is selected as the simulated rupture pipe 6, and 5 rupture diameters are obtained through calculation. Each simulated rupture will be separated by a certain distance (about 550mm) to meet the requirements of the opening and the conditions for installing control and measuring instruments. Temperature and pressure measuring points, a second venturi flowmeter 620 and a pneumatic stop valve 630 are installed on each pipe in sequence. The layout diagram of the simulated rupture pipe 6 is shown in the figure. Figure 2 As shown. Flange connections can also be replaced with compression fittings. Compression fittings offer advantages such as the elimination of gaskets and welding, excellent repetitive assembly and disassembly performance, and superior sealing properties. The flange before the simulated breach can be a high-pressure neck flange, compression fitting, or self-tightening flange.

[0053] The flanges in the experimental section primarily include: a pneumatic shutoff valve flange, a flowmeter flange, and a breach simulation flange 610. The first two flanges are high-pressure neck flanges, mated to the flanges on the shutoff valve and flowmeter. The flange before the simulated breach is a self-tightening flange. The flange connections are sealed with fully threaded studs and Type II hexagonal nuts (both made of 304 steel), and the flange connections use a concave and convex seal.

[0054] This embodiment can be further improved. The curved tube 810 is a horizontally arranged spiral tube. The sampling tube 840 is provided at the bottom of the spiral tube in the direction of gravity, for conducting the cooled water. The upper end of the sampling tube 840 is connected to the bottom of the spiral tube, and the lower end extends out of the first water tank 820, so as to conduct the cooled water to a designated location for measurement. A valve is also provided on the sampling tube 840. The steam-water collection device 8 also includes an online steam-water sensor arranged in the spiral tube, for online monitoring of the steam-water content in the sampled gas. The online steam-water sensor is communicatively connected to the online steam-water detection equipment to send the collected steam-water signal to the online steam-water detection equipment. The above-mentioned first isolation valve 830 can be a pneumatic isolation valve.

[0055] This embodiment can be further optimized. The spiral tube is arranged in the first water tank 820 and is used to condense the soda. If the contamination and sediment removal work is not carried out, the blockage will reduce the fluid flow rate inside the spiral tube, increase the residence time of the fluid in the tube, and reduce the heat transfer efficiency. The contamination will change the surface roughness and heat transfer characteristics of the spiral tube, resulting in a decrease in heat transfer efficiency. However, this spiral tube is arranged in the first water tank 820 by a bypass connected to the helium delivery pipeline, which makes it more troublesome to disassemble. This embodiment can adopt a cleaning method, combined with Figure 4 , connect the sampling tube 840 to the cleaning liquid delivery pipeline or the cleaning liquid pool, and after the spiral tube is emptied, the cleaning liquid will flow back into the spiral tube, turn on the ultrasonic oscillator (not shown in the figure) arranged in the water tank, and start ultrasonic cleaning. The ultrasonic vibration will generate high-frequency compression waves and rarefaction waves in the cleaning liquid. These waves will vibrate the dirt on the inner wall of the spiral tube. At the same time, use multiple sampling tubes 840 on the spiral tube to make the cleaning liquid flow in the spiral tube. For example, the first sampling tube 840 at one end of the spiral tube is used as a liquid inlet pipe, and the sampling tube 840 at the end is used as a liquid outlet pipe to make the cleaning liquid flow, and replace the cleaning liquid to ensure that the cleaning liquid will not be gradually contaminated by the dirt inside the spiral tube and diluted too much, so as to ensure the cleaning effect. In the specific setting, the steam-water collection device 8 may include a three-way pipe, a first isolation valve 830, a curved pipe 810 (spiral tube), a first water tank 820, a sampling tube 840 and an online steam-water sensor, as follows Figure 7 As shown, the sampling tube 840 and the online steam-water sensor are arranged at the sampling point in the figure.

[0056] The steam-water collection device 8 is designed as a closed bypass on the helium delivery pipeline 7. A first isolation valve 830 is installed on the main pipeline (helium delivery pipeline 7), and a second isolation valve 850 and a third isolation valve 860 are installed on the bypass inlet and outlet pipes, respectively. After an accident, the sampled gas flows through a spiral tube immersed in water in a first water tank 820, which contains water at room temperature and pressure. The spiral tube is located at the lowest point relative to the helium delivery pipeline 7. A sampling tube 840 is designed at the bottom of the spiral tube to drain the cooled water. An online steam-water sensor is installed on the spiral tube for online monitoring of the steam-water content in the sampled gas. The tee and spiral tube are made of the same metal as the main helium pipeline. The pipe connections are welded, and the valve connections use the same flange connection method as the main pipeline.

[0057] Reference Figures 2 to 7, Example 2, a heat exchanger rupture experimental system of a helium-cooled blanket cooling system of a fusion reactor, comprising: a first circuit, the first circuit comprising a pipeline for conveying helium; a second circuit, the second circuit comprising a pipeline for conveying water; a simulated rupture pipe 6, one end of the simulated rupture pipe 6 being connected to the first circuit, and the other end being connected to the second circuit, the simulated rupture pipe 6 being provided with a valve for controlling the opening and closing of the simulated rupture pipe 6; a steam-water collecting device 8, the steam-water collecting device 8 being provided on the helium conveying pipeline 7; a plurality of the simulated rupture pipes 6 are arranged, and in the plurality of simulated rupture pipes 6, each or part of the simulated rupture pipes 6 has a different diameter or a different diameter of a part of the sections; the steam-water collecting device The device 8 is located downstream of the connection between the simulated rupture pipe 6 and the first circuit; the steam-water collecting device 8 includes: a curved pipe 810, which is arranged on the helium delivery pipeline 7 as a bypass, and the inlet and outlet of the curved pipe 810 are provided with valves, and at least a portion of the curved pipe 810 is bent downward along the direction of gravity, and the lower part of the bent part is connected to a sampling tube 840 for draining the liquid in the pipe; a first water tank 820, and the spiral tube is arranged in the first water tank 820; a first isolation valve 830, the first isolation valve 830 is used to be arranged on the helium delivery pipeline 7, and the two ends connected to the helium delivery pipeline 7 are respectively located at the front and rear ends of the first isolation valve 830.

[0058] By setting up the above-mentioned heat exchanger rupture experimental system for the fusion reactor helium-cooled blanket cooling system, it is possible to conveniently study the impact of a heat exchanger rupture accident on the pressure and temperature of the secondary water circuit, as well as the mechanism and possible impact of the secondary water entering the helium circuit through the rupture through simulation experiments.

[0059] The first circuit comprises a high-pressure helium delivery pipe, the inlet and outlet of which are each connected to a first Venturi flowmeter 12. A second Venturi flowmeter 620 is installed on the simulated breach pipe 6, upstream of the valve on the simulated breach pipe 6. The inlet and outlet of the curved pipe 810 are connected to the high-pressure helium delivery pipe. A first isolation valve 830 is installed on the high-pressure helium delivery pipe between the two points where the curved pipe 810 connects to the pipe. The curved pipe 810 is a horizontally arranged spiral tube, with a sampling tube 840 installed at its bottom in the direction of gravity for discharging cooled water. The simulated breach pipe 6 also has a shutoff valve. A breach simulation flange is installed on the side of the shutoff valve near the second circuit, along the direction of helium flow toward the second circuit. The diameters of the outlets of the simulated breach flanges on the side near the second circuit differ among the multiple simulated breach pipes 6. The above-mentioned stop valve can adopt a pneumatic stop valve 630.

[0060] A first venturi flowmeter 12 is connected to the inlet and outlet of the high-pressure helium delivery pipe. When using the venturi flowmeter for flow measurement, not only is the flow measurement highly accurate and stable, but no additional energy input is required, and the flow measurement is achieved solely through the pressure difference of the measured fluid. The venturi flowmeter also utilizes the certain pressure loss effect of the venturi flowmeter, that is, the flow is calculated by measuring the pressure difference between the inlet and outlet. Therefore, when measuring the flow of the high-pressure helium delivery pipe, it can avoid gas leakage within the pipe and ensure the accuracy of the test measurement. The second circuit includes: a water medium delivery pipeline 9; a second water tank 10, the two ends of the water medium delivery pipeline 9 are connected to the second water tank 10; the water medium delivery pipeline 9 is connected to the first circuit via a simulated broken pipeline 6; and a pressure surge tank 11, which is connected to the second water tank 10.

[0061] A method for simulating heat exchanger pipe rupture, using the heat exchanger rupture experimental system of the fusion reactor helium-cooled blanket cooling system of Example 2 above, the method for simulating heat exchanger pipe rupture comprising the following steps:

[0062] The valve on simulated ruptured pipe 6 was opened to simulate a heat exchanger pipe rupture, and the inlet and outlet valves of the first circuit were closed to simulate triggering a shutdown signal. After the pipe rupture (after the accident), high-pressure helium in the first circuit helium cooling system would enter the second circuit (the secondary water circuit) through the simulated ruptured pipe 6, causing the pressure in the first circuit to decrease and the pressure in the second circuit to increase. Temperature, pressure, and flow rate measuring instruments were installed in each circuit to measure the changes in working fluid temperature, pressure, and flow rate at each point in the circuit in real time.

[0063] When the pressure of the second circuit is higher than the pre-qualified pressure test limit on the second circuit or the pressure of the first circuit is lower than the pre-qualified pressure test limit on the first circuit, the first circuit inlet and outlet valve closing response signal is activated, and the first circuit inlet and outlet valves are completely closed according to the predetermined closing time. When the pressure of the first circuit and the second circuit reaches equilibrium and the flow meter at the rupture measures a flow change of zero, the experiment is ended, and the experimental data collected throughout the process are sorted. At the same time, the valve of the simulated rupture pipeline 6 is closed, and the mass of helium entering the second circuit is measured by the liquid level change of the pressure-regulating tank 11 on the second circuit and the pressure and temperature change of the second circuit.

[0064] When the pressure in the second circuit is greater than or equal to the pressure in the first circuit, the water in the second circuit will flow into the first circuit (simulating the helium cooling system) through the simulated broken pipe 6. At this time, the high-temperature and high-pressure helium in the first circuit will vaporize the water into steam and entrain it in the helium. In order to test the process of the secondary side water flowing back into the first circuit after an accident, a steam-water collection device on the helium cooling pipe side is designed in the first circuit pipeline to detect the amount of water entering the first circuit. Figure 3 As shown, after the pipeline ruptures (after the accident), the first isolation valve 830 of the first circuit is closed, while the second isolation valve 850, the third isolation valve 860, and the valve on the simulated breached pipeline 6 are opened. Water vapor entrained in the helium enters the spiral tube in the first water tank 820. The cooling water flowing in the first water tank 820 forcibly cools the spiral tube, causing the vapor in the helium to condense into condensed water. After obtaining information from the online steam-water sensor in the spiral tube, the real-time steam-water content in the helium is measured using online steam-water detection equipment connected to the online steam-water sensor. After the valves on the simulated breached pipeline 6 and the first isolation valve 830 are closed, the spiral tube and the helium delivery pipe are allowed to cool to room temperature. At this point, the valve on the sampling tube 840 at the sampling point is opened, and all the water collected in the spiral tube is drained and weighed. The mass of water entering the first circuit helium system from the second circuit during the accident experiment is calculated.

[0065] Example 3: This example applies the heat exchanger breach test system of the fusion reactor helium-cooled blanket cooling system of Example 2 to the helium-cooled solid-state experimental blanket module cooling system to conduct a simulation test.

[0066] After the heat exchanger pipe ruptures, the coolant in the helium-cooled solid-state experimental blanket module cooling system is lost, and the high-pressure helium (8MPa) in the helium cooling circuit will enter the low-pressure component water cooling system (0.8MPa). Heat exchanger 4 is simulated for this situation.

[0067] like Figure 1 As shown in the figure, the main circuit of the helium-cooled solid-state experimental blanket module cooling system mainly consists of a helium blower 1, an electric heater 2, a regenerator 3, a heat exchanger 4, a dust collector 5, a regulating valve, a safety valve, and pipelines. Currently, the heat exchanger 4 of the main circuit is designed as a shell and tube heat exchanger. Under normal operating conditions, the operating pressure of the helium cooling circuit is 8MPa and the mass flow rate is 1.04kg·s -1 , the TBM inlet temperature is 300℃, the outlet temperature is 500℃, and the inlet and outlet temperatures of the water-cooled heat exchanger 4 are ~255℃ / ~70℃.

[0068] The experimental section is mainly divided into a first loop and a second loop, wherein the first loop includes an inlet and outlet, a straight pipe section, a simulated broken pipe 6 and a steam-water collecting device 8.

[0069] The second circuit includes a second circuit pipeline, a second water tank 10 , and a pressure-surge tank 11 .

[0070] Since the inlet and outlet pipes connecting the experimental section in the experimental loop are DN 200 with an inner diameter of 168.3mm, the experimental section pipe was also DN 200 with an inner diameter of 168.3mm to match the inlet and outlet pipes. Furthermore, the outer diameter of the DN 200 steel pipe with a butt-weld neck flange connecting the experimental section is 219.1mm. Based on GB17395-2008, Dimensions, Shapes, Weights, and Permissible Deviations of Seamless Steel Pipes, the steel pipe dimensions were selected to be 219.1mm outer diameter and 25mm wall thickness. This is based on the calculation of the minimum wall thickness of straight pipes subjected to internal pressure in 6.3.2.1 of GB / T32270-2015, Specification for Pressure Piping, Power Piping, and the description of allowable stresses for high-alloy steel pipes in GB 150.2-2011.

[0071] The formula (1) for determining the wall thickness based on the inner diameter of the pipe is as follows:

[0072]

[0073] Substituting the allowable stress into the above formula, it is recommended to select 0Cr17Ni12Mo2 (316 stainless steel) as the material of the experimental section pipe with this wall thickness that can meet the design pressure of 15MPa and design temperature of 625℃.

[0074] A 4000mm long straight pipe section was initially selected as the first circuit rupture test section model. According to actual needs, the simulated rupture size range was 0.153cm. 2 ~15.3cm 2 , 5 breach sizes were initially selected for accident breach design, with breach area sizes of 0.153cm 2 , 0.306cm2, 1.53cm 2 , 7.65cm 2 , 15.3cm 2 Initially, a round tube was selected as the simulated breach pipe 6. The five breach diameters were calculated to be 4.4mm, 6.2mm, 14.0mm, 31.2mm, and 44.1mm, respectively. Each simulated breach was spaced a certain distance apart (initially 550mm apart) to meet the requirements for opening the hole and installing control and measuring instruments.

[0075] Considering that the first three breaches are relatively small and very close in size, and the sizes of the last two large breaches are very similar, and that subsequent breach simulation experiments of different sizes will be conducted, DN 65 pipes are selected for all five pipes as the simulated breach pipe 6. Temperature and pressure measuring points, a second venturi flowmeter 620, and a pneumatic shut-off valve 630 are installed on each pipe in sequence. The layout of the simulated breach pipe 6 is shown in the figure below. Figure 2 As shown. The flange connection can also be replaced with a ferrule connection. The advantages of the ferrule connection are that it does not require gaskets or welding, has good repeated assembly and disassembly performance, and has good sealing performance.

[0076] A flange connection will be made at the end of each pipe to facilitate the subsequent replacement of ruptures of different sizes. The flange will be welded to the custom pipe that meets the spraying requirements. The flange connection spray rupture design is as follows: Figure 6 The flange before the simulated rupture can be a high-pressure neck flange, a ferrule or a self-tightening flange.

[0077] The operating pressure of the second circuit is 1 MPa. Considering that the operating pressure of the upstream helium cooling circuit can reach 8 MPa or even 12 MPa, calculations indicate that the blowout at the pipe rupture is critical. For experimental safety, the design pressure of the second circuit is 5 MPa and the design temperature is 200°C. Although the second circuit is filled with circulating water, the high-temperature, high-pressure helium from the first circuit will be released into the second circuit when the simulated rupture pipe 6 is opened. The outer diameter of the second circuit pipe is the same as that of the first circuit, that is, the outer diameter of the steel pipe is 219.1 mm. However, since the blowout is critical and involves water cooling, the material of the second circuit is 304 stainless steel.

[0078] According to the description of the allowable stress of high alloy steel pipes in GB 150.2-2011, the allowable stress at design temperature is 130MPa. According to the calculation of the minimum wall thickness of straight pipes under internal pressure in 6.3.2.1 of GB / T32270-2015 Pressure Piping Specification Power Piping,

[0079]

[0080] The additional thickness C is 2mm. According to GB17395-2008 Seamless Steel Pipe Dimensions, Shapes, Weights, and Permissible Deviations, the wall thickness of stainless steel pipe is 6.5mm. Therefore, the second-circuit pipe is made of 304 stainless steel, with an outer diameter of 219.1mm and a wall thickness of 6.5mm.

[0081] The steel grade used for the second water tank and the surge tank 11 cylinder is S30408. According to the description of the allowable stress of high alloy steel forgings in GB 150.2-2011, the nominal diameter of the second water tank and the surge tank 11 cylinder is DN1500 and the inner diameter is 1500mm. According to the calculation formula for the wall thickness of the cylinder under internal pressure in GB 150.3-2011,

[0082]

[0083] Substituting the values ​​into the calculation, the wall thickness is 29.412mm. Considering the corrosion allowance of 1mm and the negative deviation of the steel plate and increasing the safety margin, it is confirmed that the wall thickness of 32mm meets the requirements. The head uses a standard elliptical head with a major-minor axis ratio of 2, such as Figure 8 As shown, Di is 1500mm, hi The straight side length of the head is 25mm. The thickness of the head is calculated by the formula

[0084]

[0085] Substituting the value into the calculation formula, we get δ h It is 29.126mm. To keep consistent with the thickness of the cylinder, the final wall thickness is 32mm.

[0086] The upstream main circuit helium design pressure P1 = 15MPa, design temperature T1 = 898K, volume V1 = 2.3m 3 The original nitrogen pressure of the surge tank 11 is P2 = 1MPa, the temperature is T2 = 373K, and the volume is V2. Assuming that in an extreme case, all the helium enters the surge tank 11 of the second circuit after the spray occurs, the pressure after mixing does not exceed the design pressure P = 5MPa, the design temperature T = 473K, and the volume V = V2.

[0087] To simplify the calculation, the following formula is used

[0088]

[0089] The calculated nitrogen volume of surge tank 11 is at least 4.869m 3 , in order to meet the requirements, and the bottom of the surge tank 11 needs a certain height of water, the height of the water is tentatively set to 1m. After calculation, the total volume of the surge tank 11 needs to reach 6.459m 3 Able to meet the requirements.

[0090] To facilitate replacement of the test section, flange connections were used between the test section and the inlet and outlet pipes. According to the provisions of Section 6.2.9, Flanges, Gaskets, and Fasteners, in the "GB / T32270-2015 Specification for Pressure Piping, Power Piping," for pipes with a design temperature greater than 300°C or a nominal pressure greater than or equal to PN40, butt-weld flanges should be used. Furthermore, based on the design parameters of the test section and the operating pressures of 8MPa and 12MPa, PN100 and PN160 butt-weld steel pipe flanges (WN) with necks were selected for the inlet and outlet flanges of the test section. The flange size was DN200. The flanges in the test section primarily included: a pneumatic shutoff valve flange, a flowmeter flange, and a 610 breach simulation flange. High-pressure neck flanges were recommended for the first two flanges to mate with the flanges on the shutoff valve and flowmeter. Self-tightening flanges were recommended for the flanges before the simulated breach. Based on the pressure and temperature, we recommend using fully threaded studs and Type II hexagonal nuts (both made of 304). Select a concave or convex seal based on the pressure rating and the flange sealing type suitable for spiral wound gaskets with inner rings. Flange material: After repeated verification, combined with experience accumulated from previous experiments and research and analysis of relevant manufacturers, 12Cr1MoVG (12 chromium-molybdenum-vanadium steel) meets the design temperature and pressure requirements.

[0091] Based on the selection of the first circuit pipeline flange, the second circuit pipeline flange selects PN63 neck butt welding flange according to the second circuit design pressure and design temperature.

[0092] For the simulated breached pipeline, all six instruments are connected using butt-welded steel pipe flanges. The flange material category is 1C14 (chrome-molybdenum-chrome steel). The sealing surface should be concave and convex. Seals should be M24 fully threaded studs and Type II hexagonal nuts (both made of 304). Spiral-wound gaskets (made of 304L metal strip and flexible graphite tape) should be used as gaskets. A DN65 butt-welded steel pipe flange should be selected based on the nominal diameter of the pipeline.

[0093] Second loop water entering the first loop helium cooling system process test plan:

[0094] In order to simulate the heat exchanger pipe rupture accident, the experimental section is divided into the first circuit (helium cooling system) and the second circuit (secondary water circuit). Considering that the design rupture size is 7.65 cm 2 , 15.3cm 2 Such a large breach will result in a large amount of helium leakage in the event of an accident. Therefore, an isolation valve will be added to the secondary water circuit, i.e., the water side inlet and outlet of heat exchanger 4. The isolation valve has a shorter response time.

[0095] The valve on the simulated rupture pipe 6 is opened to simulate the rupture of the heat exchanger pipe, and the inlet and outlet valves of the first circuit are closed to simulate the triggering of the shutdown signal. After the pipe ruptures (after the accident occurs), the high-pressure helium in the first circuit, that is, the helium cooling system, will enter the second circuit, that is, the secondary side water circuit, through the simulated rupture pipe 6. The pressure in the first circuit decreases, and the pressure in the second circuit increases accordingly. When the pressure in the second circuit is greater than or equal to the pressure in the first circuit, the water in the second circuit will enter the first circuit helium cooling system through the simulated rupture pipe 6. At this time, the high-temperature and high-pressure helium in the first circuit will vaporize the water into steam and entrain it in the helium. In order to test the process of the secondary side water flowing back into the first circuit after the accident, the following is designed in the first circuit pipeline. Figure 3 The steam-water collecting device 8 is used to detect the amount of water entering the first circuit.

[0096] Under normal operating conditions in the experimental section, the first isolation valve 830 and the valves at both ends of the second water tank 10 are open, while the second isolation valve 850, the third isolation valve 860, and the valves on the simulated ruptured pipe 6 are closed. After the pipe ruptures (after the accident), the inlet and outlet valves of the first circuit and the valves at both ends of the first isolation valve 830 and the second water tank 10 are closed. The second isolation valve 850, the third isolation valve 860, and the valves on the simulated ruptured pipe 6 are opened. Water vapor entrained in the helium gas enters the spiral tube in the first water tank 820. The cooling water flowing in the first water tank 820 forcibly cools the spiral tube, causing the vapor in the helium gas to condense into condensate.

[0097] This embodiment uses sampling and weighing to determine the quality of water entering the first circuit. A sampling hole is opened at the sampling point of the spiral tube. This hole is connected to a sampling tube 840, and a needle valve is installed on the sampling tube 840. The needle valve is closed during the breach simulation experiment. After the experiment, the first isolation valve 830 is opened, the second isolation valve 850, and the third isolation valve 860 are closed. Then, the needle valve on the sampling tube 840 is opened to aspirate the condensate in the spiral tube for weighing.

[0098] At the same time, to monitor the quality of water entering the primary circuit in real time, a suitable online steam-water sensor is installed on the spiral tube for online water quality testing. This can be combined with a weighing method and a wire mesh sensor for online measurement. This online steam-water sensor monitors transient changes in steam-water content in real time.

[0099] Regarding flow measurement, a second venturi flowmeter 620 is used to measure the flow before and after the inlet and outlet of the experimental section; a second venturi flowmeter 620 is also installed on the simulated breach pipe 6 after the pneumatic stop valve 630 and before the breach to measure the flow of the helium gas spray. Figure 9As shown, due to the high temperature of helium, the pressure lead pipe is directed into a water tank to cool it down before connecting it to a pressure transmitter to measure the pressure differential, thereby measuring flow. The accuracy of the second Venturi flowmeter 620 remains unaffected within its measuring range. The design and manufacture of the flowmeter also requires determining the throttling size of the Venturi tube and other geometric dimensions based on the flow rate and pipe dimensions.

[0100] Critical flow is a phenomenon in which the flow velocity reaches its maximum value under given upstream conditions. This phenomenon occurs in both single-phase and two-phase fluids. For single-phase fluids, critical flow is well understood and usually occurs where the flow velocity at the smallest cross-section reaches the speed of sound. In this experimental loop, critical flow is only achieved in the rupture spray section, so the flow rate of the rupture spray is required to determine the flow meter selection. The outlet size, i.e. the rupture size, is 0.153 cm. 2 、0.306cm 2 、1.53cm 2 、7.65cm 2 、15.3cm 2 Substituting into the critical flow calculation formula, the critical flow rates are calculated to be 0.026kg / s, 0.0519kg / s, 0.2597kg / s, 1.2983kg / s, and 2.5965kg / s respectively.

[0101] Temperature measurement points were installed before and after the experimental section entrance and exit, before the helium spray in simulated breach pipe 6, in the secondary loop pipe, and in the water tank to monitor the system temperature in the experimental section. In this example, K-type thermocouples with a maximum range of 800°C and Class I accuracy were used for temperature measurement. High-temperature and high-pressure-resistant sealing joints were designed at the temperature measurement points on the pipes.

[0102] Regarding pressure measurement, pressure measuring points are located before the inlet and outlet of the experimental section, before the helium spray from the simulated breach pipe 6, in the second-circuit pipeline, in the water tank, and in the surge tank 11. These are used to monitor the pressure in the first and second circuits. For first-circuit pressure measurement, it is recommended to use a pressure lead pipe to cool the water in the heat exchange water tank and then connect it to a pressure transmitter for pressure measurement. Since the experimental system is designed for a maximum pressure of 15 MPa, an EJA440A high-pressure transmitter with a range of -0.1-32 MPa and an accuracy of ±0.12% is used. High-temperature and high-pressure-resistant sealing joints are designed at the pressure measuring points on the pipeline.

[0103] The above specific implementation methods further illustrate the objectives, technical solutions and beneficial effects of the present invention in detail. It should be understood that the above are only specific implementation methods of the present invention and are not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present invention should be included in the scope of protection of the present invention.

Claims

1. A heat exchanger breach simulation component for a fusion reactor helium blanket cooling system, characterized in that: include: A simulated breach pipe, one end of which is connected to the helium delivery pipeline and the other end of which is connected to the secondary water delivery pipeline, and a valve for controlling the opening and closing of the simulated breach pipe is provided on the simulated breach pipe; and A steam-water collecting device is used to be installed on the helium delivery pipeline and is located downstream of the connection between the simulated rupture pipeline and the helium delivery pipeline; The steam-water collecting device comprises: A curved pipe is provided as a bypass on the helium delivery pipeline. The inlet and outlet of the curved pipe are provided with valves. At least a portion of the curved pipe is bent downward in the direction of gravity. A sampling tube for draining the liquid in the pipe is connected to the lower part of the curved portion. a first water tank, wherein the curved pipe is arranged in the first water tank; The first isolation valve is used to be arranged on the helium delivery pipeline, and the two ends of the curved pipe connected to the helium delivery pipeline are respectively located at the front and rear ends of the first isolation valve.

2. The heat exchanger breach simulation component for a fusion reactor helium-cooled blanket cooling system according to claim 1, characterized in that: The curved pipe is a transversely arranged spiral pipe, and the sampling pipe is provided at the bottom of the spiral pipe in the gravity direction for conducting out the cooled water.

3. The heat exchanger breach test system of the helium-cooled blanket cooling system of the fusion reactor is characterized by: include: a first circuit comprising a pipeline for conveying helium gas; a second circuit comprising a pipe for conveying water; A simulated breach pipe, one end of which is connected to the first circuit and the other end of which is connected to the second circuit, and a valve for controlling the opening and closing of the simulated breach pipe is provided on the simulated breach pipe; A steam-water collecting device, which is arranged on the helium delivery pipeline; There are multiple simulated rupture pipes, and among the multiple simulated rupture pipes, each or some of the simulated rupture pipes have different diameters or some sections have different diameters; The steam-water collecting device is located downstream of the connection between the simulated breach pipe and the first circuit; The steam-water collecting device comprises: A curved pipe is provided as a bypass on the helium delivery pipeline. The inlet and outlet of the curved pipe are provided with valves. At least a portion of the curved pipe is bent downward in the direction of gravity. A sampling tube for draining the liquid in the pipe is connected to the lower part of the curved portion. a first water tank, wherein the curved pipe is arranged in the first water tank; The first isolation valve is used to be arranged on the helium delivery pipeline, and the two ends of the curved pipe connected to the helium delivery pipeline are respectively located at the front and rear ends of the first isolation valve.

4. The heat exchanger breach test system for the fusion reactor helium-cooled blanket cooling system according to claim 3, characterized in that: The first circuit includes a high-pressure helium gas delivery pipe, the inlet and outlet of which are respectively connected to a venturi flowmeter; A Venturi flowmeter is provided on the simulated breach pipe.

5. The heat exchanger breach test system for the fusion reactor helium-cooled blanket cooling system according to claim 4, characterized in that: The inlet and outlet ends of the curved pipe are connected to the high-pressure helium delivery pipe. A first isolation valve arranged on the high-pressure helium delivery pipe is provided between the two places where the curved pipe is connected to the high-pressure helium delivery pipe.

6. The heat exchanger breach test system for the fusion reactor helium-cooled blanket cooling system according to claim 5, characterized in that: The curved pipe is a transversely arranged spiral pipe, and the sampling pipe is provided at the bottom of the spiral pipe in the gravity direction for conducting out the cooled water.

7. The heat exchanger breach test system for the fusion reactor helium-cooled blanket cooling system according to claim 3, characterized in that: A stop valve is also arranged on the simulated breach pipeline, and a breach simulation flange is provided on a side of the stop valve close to the second circuit along the direction of helium flowing toward the second circuit.

8. The heat exchanger breach test system for the fusion reactor helium-cooled blanket cooling system according to claim 3, characterized in that: The second circuit includes: Water medium transmission pipeline; a second water tank, to which both ends of the water medium delivery pipeline are connected; the water medium delivery pipeline is connected to the first circuit through a simulated broken pipeline; A pressure stabilizing tank is connected to the second water tank.

9. A method for simulating heat exchanger pipe rupture, characterized in that: Using the heat exchanger rupture experimental system of the fusion reactor helium-cooled blanket cooling system according to claim 8, the method for simulating the rupture of the heat exchanger pipe comprises the following steps: After the helium enters the second circuit from the simulated ruptured pipe; When the pressure of the second circuit is higher than the preset pressure test limit of the second circuit or the pressure of the first circuit is lower than the preset pressure test limit of the first circuit, the closing response signal of the inlet and outlet valves of the first circuit is activated; The mass of helium entering the second circuit is measured by detecting the liquid level information in the pressure-surge tank of the second circuit and the pressure and temperature information of the second circuit; When the pressure in the second circuit is greater than or equal to the pressure in the first circuit, the water vapor entrained in the helium will enter the spiral tube in the first water tank. The cooling water flowing in the first water tank will forcefully cool the spiral tube to condense the water vapor in the helium into condensed water. Open the valve of the sampling tube and drain all the water collected in the spiral tube and weigh it to obtain the mass of water entering the first loop helium system from the second loop during the accident experiment.

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