CN116403743A - Heat exchanger break simulation system and method for fusion reactor helium cold cladding cooling system - Google Patents
Heat exchanger break simulation system and method for fusion reactor helium cold cladding cooling system Download PDFInfo
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
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Abstract
The invention relates to a heat exchanger break experiment system and a heat exchanger break experiment method of a fusion reactor helium cold cladding cooling system, wherein the heat exchanger break experiment system of the fusion reactor helium cold cladding cooling system comprises: a first circuit for delivering helium gas; a second circuit for delivering water; a simulated break pipeline, wherein one end of the simulated break pipeline is communicated with the first loop, the other end of the simulated break pipeline is communicated with the second loop, and a valve is arranged on the simulated break pipeline; and the vapor-water collecting device is arranged on the helium gas conveying pipeline. Through setting up foretell fusion reactor helium cold blanket cooling system's heat exchanger experimental system that breaks, accessible analogue test, the influence to pressure, the temperature of secondary side water circuit after the heat exchanger breaks accident to and the mechanism and the influence that probably cause that secondary side water gets into the helium circuit through the break.
Description
Technical Field
The invention relates to maintenance of a fusion reactor helium cold cladding cooling system, in particular to a heat exchanger break simulation assembly for the fusion reactor helium cold cladding cooling system, a heat exchanger break experiment system for the fusion reactor helium cold cladding cooling system and a method for simulating pipeline breakage of a heat exchanger.
Background
With the growing demand for energy by humans, the lack of limited fossil fuel resources, and the increasing importance of environmental quality, we have to consider new clean, long-lasting, renewable new energy sources. Among them, nuclear fusion energy is considered as the most potential clean energy source due to the characteristics of abundant nuclear fuel, no pollution, no high-radioactivity waste and the like, and fusion energy engineering is a challenging task, and there are a plurality of problems, such as steady state or long-time pulse operation of a fusion reactor, system safety problems in case of accidents and the like. In order to solve the problem of fusion reactor safety in engineering, fusion reactor system safety design and accident analysis play an increasingly important role in fusion reactor design and development. With the start of the engineering design of the international thermonuclear fusion experimental reactor ITER (International Thermonuclear Experimental Reactor), fusion research gradually enters an engineering stage, and safety design and accident analysis are also introduced into the process of project design and development.
In the early stage of fusion reactor design, system safety design and accident analysis are also performed. In the design of fusion stacks, the accident analysis work has 2 main aspects: (1) each system and safety control function are verified through thermal hydraulic transient analysis, and the nuclear accident result is ensured to be in a controllable and buffering range; (2) and according to the calculation result, analyzing the defects of each system design and optimizing so that the system is optimized in economy and safety. Helium cold cladding system is the key system for realizing fusion energy application in fusion reactor, and accident analysis is necessary work for ensuring safe operation of fusion reactor. The helium cold cladding system has good improvement on thermal performance and mechanical performance through design updating and accident analysis of several generations. However, in order to verify the accuracy of safety design and accident analysis, design-basis accident verification experiments are also required to be carried out based on the helium cold cladding cooling system design in the fusion reactor.
The accident of the broken pipe of the heat exchanger of the helium cooling cladding system is one of the accidents which the helium cooling cladding system must analyze, and also relates to the design of the integral water cooling system of the fusion reactor. After the pipeline of the heat exchanger is broken, the coolant of the cooling system of the helium cold solid state experiment cladding module is lost, and high-pressure helium (more than 8 MPa) in the helium cold loop can enter a low-pressure water cooling system (0.8 MPa). The influence on the pressure and the temperature of the secondary side water loop after the heat exchanger breaks through an accident experiment and the mechanism and the possible influence of the secondary side water entering the helium loop through the break are researched. The experimental measurement method and experimental section design for the helium gas spraying and the secondary side water backflow entering the helium cooling system of the helium working medium heat exchanger pipeline rupture accident still belong to the blank at present.
Disclosure of Invention
The invention aims to solve the problem of providing a heat exchanger break simulation system and a heat exchanger break simulation method of a fusion reactor helium cold cladding cooling system suitable for the design characteristics of a helium cooling system when experimental verification is carried out on the heat exchanger break accident of the fusion reactor helium cold cladding cooling system, wherein the system can be used for testing the spraying process of helium to a water side after the heat exchanger break accident and the backflow amount of water into a helium pipeline after the accident so as to conveniently study the influence on the pressure and the temperature of a secondary side water loop after the heat exchanger break accident and the mechanism and the possible influence of the secondary side water entering the helium loop through the break.
A first aspect of the invention provides a heat exchanger break simulating assembly for a fusion reactor helium cold blanket cooling system, comprising: the device comprises a simulated break pipeline, a first pipeline and a second pipeline, wherein one end of the simulated break pipeline is used for being communicated with a helium gas conveying pipeline, the other end of the simulated break pipeline is used for being communicated with a secondary side water conveying pipeline, and a valve for controlling the opening and closing of the simulated break pipeline is arranged on the simulated break pipeline; the steam-water collecting device is arranged on the helium gas conveying pipeline and is positioned at the downstream of the joint of the simulated break pipeline and the helium gas conveying pipeline; the soda water collecting device comprises: the bent pipe is arranged on the helium gas conveying pipeline as a bypass, the inlet and the outlet of the bent pipe are provided with valves, at least one part of the bent pipe is bent downwards along the gravity direction, and the lower part of the bent part is communicated with a sampling pipe for guiding out liquid in the pipe; a first water tank in which the spiral pipe is disposed; the first isolation valve is used for being arranged on the helium gas conveying pipeline, and two ends of the spiral pipe connected with the helium gas conveying pipeline are respectively located at the front end and the rear end of the first isolation valve. A plurality of simulated break lines of different diameters or at least a portion of the tube segments of different diameters may be provided to simulate different break sizes disposed between the helium gas delivery line and the secondary side water delivery line. The simulation break pipelines with different diameters or at least partial pipe sections are arranged, so that the safety is improved, experiments are carried out in safer environments, the risk of direct leakage of high-pressure gas is avoided, meanwhile, the influence of breaks with different sizes on the gas flow characteristics can be studied, multiple groups of experiments are carried out, references are provided for break processing under actual conditions, the break simulation is carried out in a pipeline mode, the experiment cost is reduced, and the cost of manufacturing break experimental equipment with different sizes is avoided.
The heat exchanger crack simulation assembly for the fusion reactor helium cold cladding cooling system is adopted to form an experimental system for detecting water backflow into the helium cooling system, so that a method for testing backflow steam-water quality is realized. In this heat exchanger breach simulation subassembly, can be with foretell simulation breach pipeline arrangement between helium transfer line and secondary side water transfer line, the emergence breach accident of the heat exchanger between these two systems is simulated, arranges foretell vapour and water collection device on helium transfer line to because of pressure differential, behind the rivers in secondary side water transfer line to helium transfer line, through the vapour and water condensation in the pipe of foretell spiral pipe, in order to make things convenient for the water quality that advances in the helium system in the statistics accident experiment.
In order to study the influence on the pressure and the temperature of a secondary side water loop after a heat exchanger rupture accident and the mechanism and the possible influence caused by the secondary side water entering a helium loop through a rupture, aiming at the process that helium is sprayed out and secondary side water flows back into a helium cooling system after a heat exchanger pipeline rupture accident, the heat exchanger rupture simulation component for the fusion reactor helium cooling cladding cooling system is used for reflecting the influence on the pressure and the temperature of an external environment after the rupture accident.
In some possible embodiments, the curved pipe is a transversely arranged spiral pipe, the bottom of which in the direction of gravity is provided with the sampling pipe for guiding out the cooled water. The upper end of the sampling tube is connected to the bottom of the spiral tube, and the lower end of the sampling tube extends out of the first water tank to guide the cooled water to a designated position for measurement. The sampling tube is also provided with a valve.
In some possible embodiments, the steam-water collection device further comprises 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 in communication connection with online steam-water detection equipment and is used for sending the collected steam-water signals to the online steam-water detection equipment.
The second aspect of the invention provides a heat exchanger break experiment system of a fusion reactor helium cold cladding cooling system, comprising: a first circuit comprising a line for delivering helium; a second circuit comprising a pipe for transporting water; the device comprises a simulated break pipeline, a first loop and a second loop, wherein one end of the simulated break pipeline is communicated with the first loop, the other end of the simulated break pipeline is communicated with the second loop, and a valve for controlling the simulated break pipeline to be opened and closed is arranged on the simulated break pipeline; the vapor-water collecting device is arranged on the helium gas conveying pipeline; the simulated break pipelines are arranged in a plurality, and in the simulated break pipelines, the diameter of each or part of the simulated break pipelines is different or the diameter of part of the simulated break pipelines is different; the steam-water collecting device is arranged at the downstream of the joint of the simulated break pipeline and the first loop; the soda water collecting device comprises: the bent pipe is arranged on the helium gas conveying pipeline as a bypass, the inlet and the outlet of the bent pipe are provided with valves, at least one part of the bent pipe is bent downwards along the gravity direction, and the lower part of the bent part is communicated with a sampling pipe for guiding out liquid in the pipe; a first water tank in which the spiral pipe is disposed; the first isolation valve is used for being arranged on the helium gas conveying pipeline, and two ends of the spiral pipe connected with the helium gas conveying pipeline are respectively located at the front end and the rear end of the first isolation valve. The first circuit described above may be used as a simulated helium cooling system or as part of a simulated helium cooling system.
The second loop simulates a secondary side water delivery system.
Through setting up foretell fusion reactor helium cold blanket cooling system's heat exchanger experimental system that breaks, accessible analogue test, the influence to pressure, the temperature of secondary side water circuit after the heat exchanger breaks accident to and the mechanism and the influence that probably cause that secondary side water gets into the helium circuit through the break.
In some possible embodiments, the first circuit comprises a high-pressure helium pipe conveying pipe, and a venturi flowmeter is connected to an inlet and an outlet of the high-pressure helium pipe conveying pipe respectively; and a venturi flowmeter is arranged on the simulated break pipeline and is positioned at the upstream of the valve on the simulated break pipeline.
In some possible embodiments, the two ends of the inlet and outlet of the curved tube are communicated with the high-pressure helium tube conveying tube, and a first isolation valve arranged on the high-pressure helium tube conveying tube is arranged between the two parts of the curved tube, which are communicated with the high-pressure helium tube conveying tube.
In some possible embodiments, the curved pipe is a transversely arranged spiral pipe, the bottom of which in the direction of gravity is provided with the sampling pipe for guiding out the cooled water.
In some possible embodiments, a stop valve is further arranged on the simulated break pipeline, and a break simulated flange is arranged on one side, close to the second loop, of the stop valve along the direction of helium flowing to the second loop; among the plurality of simulated break lines, the break simulation flanges of the simulated break lines have different diameters of outlets on a side of the simulated flange that is adjacent to the second circuit.
In some possible embodiments, the second loop comprises: an aqueous medium delivery line; the two ends of the water medium conveying pipeline are communicated with the second water tank; the water medium conveying pipeline is connected with the first loop through a simulated break pipeline; and the pressure stabilizing tank is communicated with the second water tank.
The third aspect of the invention also provides a method for simulating the breakage of a heat exchanger pipeline, which adopts the heat exchanger break experimental system of the fusion reactor helium cold cladding cooling system of the second aspect and the improvement thereof, and the method for simulating the breakage of the heat exchanger pipeline comprises the following steps:
closing a first loop inlet and outlet valve for simulating and triggering a shutdown signal;
after helium enters the second loop from the simulated break pipeline;
when the pressure of the second loop is higher than a preset pressure test limit value on the second loop or the pressure of the first loop is lower than a preset pressure test limit value on the first loop, starting a first loop inlet and outlet valve closing response signal;
the inlet and outlet valves of the first loop are completely closed according to preset closing time, when the pressure of the first loop and the pressure of the second loop reach balance, and when the flow measured by the flow meter of the simulated break pipeline changes to zero, the experiment is ended, experimental data are collected, the valve of the simulated break pipeline is closed, and the mass of helium entering the second loop is measured by detecting the liquid level information in the pressure stabilizing tank of the second loop and the pressure temperature information of the second loop;
When the pressure of the second loop is greater than or equal to the pressure in the first loop, closing a first isolation valve on the first loop, and opening a second isolation valve, a third isolation valve and a valve on a simulated break pipeline to enable water vapor entrained in helium to enter a spiral pipe in a first water tank, wherein cooling water flowing in the first water tank forcibly cools the spiral pipe to enable the vapor in the helium to be condensed into condensed water;
the online steam-water detection equipment is used for detecting the steam-water content in the real-time helium, after the valve of the simulated break pipeline and the first isolation valve are closed, the spiral pipe and the main loop pipeline are cooled to normal temperature in a static mode, at the moment, the valve of the sampling pipe is opened, and all water collected in the spiral pipe is discharged and weighed, so that the water quality of the helium entering the first loop system from the second loop in an accident experiment is obtained.
Fusion reactor engineering is currently in a preliminary design stage, a helium cooling cladding system is one of core systems of the fusion reactor, the design of the cladding cooling system is complex, and experimental data support of safety accident results is lacking, the invention develops an experimental bench suitable for helium cooling system design benchmark accidents (heat exchanger pipeline breakage) by utilizing the existing helium cooling system validation experimental bench on the basis of the design of a square helium cooling cladding system in an international thermonuclear fusion reactor (ITER),
The heat exchanger break experiment system of the fusion reactor helium-cooling cladding cooling system and the method for simulating the breakage of the heat exchanger pipeline can fill the gap of pressure and temperature measurement design and method after the break accident of the heat exchanger of the helium-cooling cladding system accident experiment in the field of fusion reactors, and the gap of test platform design and method for water backflow entering the helium-cooling loop after the accident, thereby providing a high-efficiency system and method for the accident safety verification of the helium-cooling cladding system in the fusion reactor engineering design stage.
Drawings
The accompanying drawings, which are included to provide a further understanding of embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiments of the invention. In the drawings:
FIG. 1 is a schematic diagram illustrating a current helium cold cure experiment cladding module cooling system in an embodiment;
FIG. 2 is a schematic diagram for explaining a heat exchanger break simulating assembly for a fusion reactor helium cold blanket cooling system in example 1 and a heat exchanger break experimental system for a fusion reactor helium cold blanket cooling system in example 2;
fig. 3 is a schematic view for explaining the soda water collection device in embodiments 1 and 2;
FIG. 4 is a schematic view for explaining washing of the soda water collection device in examples 1 and 2;
FIG. 5 is a schematic diagram of two different pipe diameter break simulation flanges for illustrating the simulated break pipes in examples 1 and 2;
FIG. 6 is a modeling diagram of a heat exchanger breach experiment system for illustrating a fusion reactor helium cold blanket cooling system in example 2;
FIG. 7 is a modeling diagram for explaining the soda water collection device in examples 1 and 2;
fig. 8 is a head structure diagram for explaining the second tank and the surge tank body in example 2;
fig. 9 is a schematic diagram for explaining the operation principle of the venturi meter in embodiments 1 and 2;
reference numerals and corresponding part names:
1-helium blower, 2-electric heater, 3-regenerator, 4-heat exchanger, 5-dust remover, 6-simulated break pipeline, 610-break simulated flange, 620-second venturi flowmeter, 630-pneumatic stop valve, 7-helium delivery line, 8-steam-water collecting device, 810-curved pipe, 820-first water tank, 830-first isolation valve, 840-sampling tube, 850-second isolation valve, 860-third isolation valve, 9-aqueous medium delivery line, 10-second water tank, 11-surge tank, 12-first venturi flowmeter.
Detailed Description
For the purpose of making apparent the objects, technical solutions and advantages of the present invention, the present invention will be further described in detail with reference to the following examples and the accompanying drawings, wherein the exemplary embodiments of the present invention and the descriptions thereof are for illustrating the present invention only and are not to be construed as limiting the present invention.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. However, it will be apparent to one of ordinary skill in the art that: no such specific details are necessary to practice the invention. In other instances, well-known structures, circuits, materials, or methods have not been described in detail in order not to obscure the invention.
Throughout the specification, references to "one embodiment," "an embodiment," "one example," or "an example" mean: a particular feature, structure, or characteristic described in connection with the embodiment or example is included within at least one embodiment of the invention. Thus, the appearances of the phrases "in one embodiment," "in an example," or "in 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 any suitable combination and/or sub-combination in one or more embodiments or examples. Moreover, those of ordinary skill in the art will appreciate that the illustrations provided herein are for illustrative purposes and that the illustrations are not necessarily drawn to scale. The term "and/or" as used herein includes any and all combinations of one or more of the associated listed items.
In the description of the present invention, it should be understood that the terms "front", "rear", "left", "right", "upper", "lower", "vertical", "horizontal", "high", "low", "inner", "outer", etc. indicate orientations or positional relationships based on the drawings, are merely for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the apparatus or elements referred to must have a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the scope of the present invention.
Referring to fig. 1, a main loop of a helium cooling solid state experiment cladding module cooling system mainly comprises a helium fan 1, an electric heater 2, a heat regenerator 3, a heat exchanger 4, a dust remover 5, a regulating valve, a safety valve, a pipeline and the like, and the heat exchanger 4 of the main loop is designed into a shell-and-tube heat exchanger at present.
Aiming at the process that helium is sprayed out of a heat exchanger pipeline breakage accident and secondary side water flows backwards into a first loop, in order to study the influence on the pressure and the temperature of the secondary side water loop after the heat exchanger breakage accident and the mechanism and the possible influence caused by the secondary side water entering the helium loop through the break, the embodiment designs the simulated break pipeline 6 with different break sizes so as to reflect the influence on the pressure and the temperature of the external environment after the accident occurs under the different break sizes.
Referring to fig. 2 to 7, embodiment 1, a heat exchanger break simulation assembly for a fusion reactor helium cold blanket cooling system, comprising: a simulated break pipeline 6, wherein one end of the simulated break pipeline 6 is used for being communicated with the helium gas conveying pipeline 7, the other end of the simulated break pipeline 6 is used for being communicated with the secondary side water conveying pipeline, and a valve for controlling the simulated break pipeline 6 to be opened and closed is arranged on the simulated break pipeline 6; the steam-water collecting device 8 is arranged on the helium gas conveying pipeline 7, and the arrangement position of the steam-water collecting device 8 is positioned at the downstream of the joint of the simulated break pipeline 6 and the helium gas conveying pipeline 7; the soda water collection device 8 includes: a curved tube 810, the curved tube 810 being arranged as a bypass on the helium gas delivery pipeline 7, an inlet and an outlet of the curved tube 810 being provided with a valve, at least a part of the curved tube 810 being bent downwards along the gravity direction, a sampling tube 840 being communicated with the lower part of the bent part for guiding out the liquid in the tube; a first water tank 820, the spiral pipe being disposed within the first water tank 820; the first isolation valve 830 is configured to be disposed on the helium gas delivery pipeline 7, and two ends of the spiral pipe connected to the helium gas delivery pipeline 7 are respectively located at the front end and the rear end of the first isolation valve 830.
A plurality of simulated break lines 6 of different diameters or at least of part of the pipe sections may be provided to simulate different break sizes arranged between the helium gas delivery line 7 and the secondary side water delivery line. The simulated break pipeline 6 simulates breaks of different sizes, and can adopt a break simulation flange 610 with different calibers arranged on one side of a valve close to the secondary side water conveying pipeline, as shown in fig. 5, the pipe diameter on one side of the valve close to the secondary side water conveying pipeline is changed, and the different simulated breaks are adjusted, so that the replacement and adjustment are convenient.
The heat exchanger break simulation assembly for the fusion reactor helium cold cladding cooling system is arranged on the helium conveying pipeline 7 and between the helium conveying pipe and the secondary side water conveying pipeline, and is used for performing simulation tests so as to conveniently reflect the influence on the pressure and the temperature of the external environment after a break accident occurs.
The simulated break pipeline 6 is connected with a neck butt welding flange, namely the simulated break pipeline 6 can be divided into two sections of pipelines which are close to the helium gas conveying pipeline 7 and are used for arranging various devices, and the other section of the pipeline which is close to the secondary side water conveying pipeline is connected with the section through the neck butt welding flange, and the size and the wall thickness of the steel pipe are selected according to GB17395-2008 seamless steel pipe size, appearance, weight and allowable deviation. According to the calculation of the minimum wall thickness of a straight pipe subjected to internal pressure in GB/T32270-2015 pressure pipeline standard power pipeline 6.3.2.1 and the description of allowable stress of a high alloy steel pipe in GB 150.2-2011, a wall thickness formula (1) is determined according to the inner diameter of the pipe as follows:
And carrying allowable stress into the experimental section pipe material, and selecting experimental section pipe materials capable of meeting the wall thickness under the conditions of design pressure and design temperature according to the table look-up of the calculation result.
And selecting a straight pipe section with a certain length as a simulated break experiment section model, selecting 5 break sizes according to the simulated break size range according to actual demand conditions to perform accident break design, selecting a circular pipe as a simulated break pipeline 6, and obtaining 5 break diameters through calculation. Each simulated break is separated by a certain distance (about 550 mm) to meet the requirements of opening holes and the conditions of installing control and measuring instruments. Each of the pipes is installed with a temperature and pressure measuring point, a second venturi flow meter 620 and a pneumatic cut-off valve 630 in turn. The simulated break pipe 6 is shown in figure 2. The flange connection can also be replaced by a bayonet connection. The clamping sleeve connection has the advantages that a gasket is not required to be added, welding is not required, and the repeated assembly and disassembly performance is good and the sealing performance is also good. The flange before the simulated break can be selected from a high-pressure necked flange, a clamping sleeve or a self-tightening flange.
The flange of experimental section mainly includes: pneumatic shut-off valve flange, flow meter flange, and breach simulation flange 610. The flanges of the first two parts adopt high-pressure necked flanges, are matched with self-contained flange sheets of the stop valve and the flowmeter, and the flange before the simulated break adopts a self-tightening flange. The sealing piece for the flange connection adopts a full-thread stud and a type II hexagonal nut (304 materials), and the sealing mode for the flange connection adopts concave-convex surface sealing.
This embodiment may be further modified in that the curved pipe 810 is a transversely arranged spiral pipe, the bottom of which in the gravity direction is provided with the sampling pipe 840 for guiding out the cooled water. The upper end of the sampling tube 840 is connected to the bottom of the spiral tube, and the lower end thereof is protruded from the first water tank 820 to guide the cooled water to a designated position for measurement. The valve is also provided on the sampling tube 840. The steam-water collecting device 8 further comprises an on-line steam-water sensor arranged in the spiral pipe for on-line monitoring of the steam-water content in the sampled gas. The online steam-water sensor is in communication connection with online steam-water detection equipment and is used for sending the collected steam-water signals to the online steam-water detection equipment. The first isolation valve 830 described above may employ a pneumatic isolation valve.
This embodiment may be further optimized in that the coil is disposed in the first water tank 820 and is used to condense the soda, if the dirt removal and sediment removal is not performed, the resulting blockage may reduce the fluid flow rate inside the coil, so that the residence time of the fluid in the tube is increased and the heat transfer efficiency is reduced; while contamination can alter the surface roughness and heat transfer characteristics of the interior of the coil, resulting in reduced heat transfer efficiency, the present coil is disposed in the first tank 820 using a bypass connected to the helium delivery line, which can be cumbersome to disassemble. In this embodiment, a cleaning method may be adopted, and referring to fig. 4, a sampling tube 840 is connected to a cleaning solution delivery pipe or a cleaning solution tank, after the spiral tube is emptied, the cleaning solution is returned to the spiral tube, an ultrasonic oscillator (not shown in the figure) disposed in the water tank is started to start ultrasonic cleaning, high-frequency compression waves and sparse waves are generated in the cleaning solution by ultrasonic vibration, the waves vibrate dirt on the inner wall of the spiral tube, meanwhile, the cleaning solution flows in the spiral tube by using a plurality of sampling tubes 840 on the spiral tube, for example, a first sampling tube 840 at one end of the spiral tube is used as a liquid inlet tube, a sampling tube 840 at the end is used as a liquid outlet tube to flow the cleaning solution, and the cleaning solution is replaced to ensure that the cleaning solution is not polluted and diluted excessively by dirt inside the spiral tube gradually, so as to ensure the cleaning effect. In a specific arrangement, the present soda collection device 8 may comprise a tee, a first isolation valve 830, a curved tube 810 (spiral tube), a first water tank 820, a sampling tube 840 and an on-line soda sensor, as shown in fig. 7 below, the sampling tube 840 and the on-line soda sensor being disposed at sampling points in the figure.
The steam-water collecting device 8 is designed as a closed bypass on the helium gas conveying pipeline 7, a first isolation valve 830 is arranged on the main pipeline (the helium gas conveying pipeline 7), and a second isolation valve 850 and a third isolation valve 860 are respectively arranged on the bypass inlet pipe. The sampled gas flows through the spiral pipe after an accident, and the spiral pipe is soaked in water in the first water tank 820, wherein the water in the first water tank 820 is normal temperature and normal pressure. A spiral is arranged at the lowest position with respect to the helium gas delivery line 7, and a sampling tube 840 is designed at the bottom of the spiral for guiding out cooled water, and an on-line steam-water sensor is arranged on the spiral for on-line monitoring of the steam-water content in the sampled gas. The three-way pipe and the spiral pipe are made of metal materials identical to those of the main helium pipeline, the pipeline connection is welding, and the valve connection is in the same flange connection mode with the main pipeline.
Referring to fig. 2 to 7, embodiment 2 is a heat exchanger break experiment system of a fusion reactor helium cold blanket cooling system, comprising: a first circuit comprising a line for delivering helium; a second circuit comprising a pipe for transporting water; the simulated break pipeline 6, one end of the simulated break pipeline 6 is communicated with the first loop, the other end of the simulated break pipeline 6 is communicated with the second loop, and a valve for controlling the simulated break pipeline 6 to be opened and closed is arranged on the simulated break pipeline 6; a vapor-water collecting device 8, the vapor-water collecting device 8 being provided on the helium gas delivery line 7; a plurality of simulated break pipes 6 are arranged, and in the plurality of simulated break pipes 6, each or part of the simulated break pipes 6 have different diameters or different diameters of partial sections; the steam-water collecting device 8 is arranged at a position downstream of the joint of the simulated break pipeline 6 and the first loop; the soda water collection device 8 includes: a curved tube 810, the curved tube 810 being arranged as a bypass on the helium gas delivery pipeline 7, an inlet and an outlet of the curved tube 810 being provided with a valve, at least a part of the curved tube 810 being bent downwards along the gravity direction, a sampling tube 840 being communicated with the lower part of the bent part for guiding out the liquid in the tube; a first water tank 820, the spiral pipe being disposed within the first water tank 820; the first isolation valve 830 is configured to be disposed on the helium gas delivery pipeline 7, and two ends of the spiral pipe connected to the helium gas delivery pipeline 7 are respectively located at the front end and the rear end of the first isolation valve 830.
Through setting up foretell fusion reactor helium cold blanket cooling system's heat exchanger experimental system that breaks, accessible analogue test, the influence to pressure, the temperature of secondary side water circuit after the heat exchanger breaks accident to and the mechanism and the influence that probably cause that secondary side water gets into the helium circuit through the break.
The first loop includes: the first loop comprises a high-pressure helium pipe conveying pipe, and the inlet and the outlet of the high-pressure helium pipe conveying pipe are respectively connected with a first venturi flowmeter 12; a second venturi meter 620 is provided on the simulated break line 6, the second venturi meter 620 being located upstream of the valve on the simulated break line 6. The inlet and outlet ends of the curved tube 810 are communicated with the high-pressure helium pipe conveying pipe, and a first isolation valve 830 arranged on the high-pressure helium pipe conveying pipe is arranged between the two positions where the curved tube 810 is communicated with the high-pressure helium pipe conveying pipe. The curved pipe 810 is a spiral pipe arranged laterally, and the bottom of the spiral pipe in the gravity direction is provided with the sampling pipe 840 for guiding out the cooled water. A stop valve is further arranged on the simulated break pipeline 6, and a break simulation flange is arranged on one side, close to the second loop, of the stop valve along the direction of helium flowing to the second loop; of the plurality of simulated break lines 6, the break simulation flanges of the simulated break lines 6 have different outlet diameters on the side close to the second circuit. The shut-off valve described above may employ a pneumatic shut-off valve 630.
The inlet and the outlet of the high-pressure helium pipe conveying pipe are respectively connected with the first venturi flowmeter 12, when the flow measurement is carried out by adopting the venturi flowmeter, the accuracy is high, the stability is good, and the flow measurement is realized only by the pressure difference of the measured fluid without other extra energy input, and the flow is calculated by utilizing the certain pressure loss function of the venturi flowmeter, namely by measuring the pressure difference between the inlet and the outlet, so that the leakage of gas in the pipeline can be avoided in the flow measurement of the high-pressure helium pipe, and the test measurement accuracy is ensured. The second circuit includes: an aqueous medium delivery line 9; a second water tank 10, two ends of the water medium conveying pipeline 9 are communicated with the second water tank 10; the water medium conveying pipeline 9 is connected with the first loop through the simulated break pipeline 6; a surge tank 11, the surge tank 11 being connected to the second water tank 10.
A method for simulating heat exchanger tube cracking using the heat exchanger cracking experimental system of fusion reactor helium cold blanket cooling system of example 2 above, the method for simulating heat exchanger tube cracking comprising the steps of:
the opening of the valve on the simulated break pipeline 6 is used for simulating the break of the pipeline of the heat exchanger, and the closing of the inlet and outlet valve of the first loop is used for simulating the triggering of the shutdown signal. After the pipeline breaks (after an accident occurs), high-pressure helium in the helium cooling system of the first loop enters a second loop (secondary side water loop) through the simulated broken pipeline 6, the pressure in the first loop is reduced, the pressure in the second loop is increased, temperature, pressure and flow measuring instruments are arranged on each loop, and the temperature, pressure and flow changes of working media at each point of the loop are measured in real time through the temperature, pressure and flow measuring instruments on the loop.
When the pressure of the second loop is higher than the pre-examination pressure test limit value on the second loop or the pressure of the first loop is lower than the pre-examination pressure test limit value on the first loop, a first loop inlet and outlet valve closing response signal is started, the first loop inlet and outlet valve is completely closed according to preset closing time, when the pressure of the first loop and the pressure of the second loop reach balance, the flow measured by a flow meter at a break is zero, the experiment is ended, experimental data collected in the whole process are collated, meanwhile, the valve simulating the break pipeline 6 is closed, and the mass of helium entering the second loop is measured through the liquid level change of the surge tank 11 on the second loop and the pressure temperature change of the second loop.
When the pressure of the second loop is greater than or equal to the pressure in the first loop, water in the second loop enters the first loop (simulated helium cooling system) through the simulated break pipeline 6, and high-temperature and high-pressure helium in the first loop can enable water to be gasified into steam and entrained in the helium, so that a process that secondary side water flows backwards into the first loop after an accident occurs is tested, and a helium cooling pipeline side steam-water collecting device is designed in the first loop pipeline and used for detecting the water quantity entering the first loop. As shown in fig. 3 of the steam-water detection system, after the pipe breaks (after an accident occurs), the first isolation valve 830 of the first loop is closed, the second isolation valve 850, the third isolation valve 860 and the valves on the simulated break pipe 6 are opened, and the water vapor entrained in the helium gas enters the spiral pipe in the first water tank 820, so that the cooling water flowing in the first water tank 820 forcibly cools the spiral pipe to condense the vapor in the helium gas into condensed water. After acquiring information through an online steam-water sensor in the spiral pipe, detecting the steam-water content in real-time helium by using online steam-water detection equipment in communication connection with the online steam-water sensor, after closing a valve on the simulated break pipeline 6 and the first isolation valve 830, statically cooling the spiral pipe and the helium conveying pipe to normal temperature, opening a sampling pipe 840 valve at a sampling point at the moment, fully discharging and weighing water collected in the spiral pipe, and counting the water quality entering a first loop helium system from a second loop in an accident experiment.
Example 3 in this example, a simulation test was performed on the heat exchanger break test system of the fusion reactor helium-cold clad cooling system of example 2 described above for application to a helium-cold solid state test clad module cooling system.
After the heat exchanger pipeline breaks, the coolant of the helium cold solid state experiment cladding module cooling system is lost, high-pressure helium gas (8 MPa) in the helium cold loop can enter a low-pressure element water cooling system (0.8 MPa), and the heat exchanger 4 in the helium cold loop is simulated aiming at the situation.
As shown in fig. 1, the main loop of the helium cold solid state experiment cladding module cooling system mainly comprises a helium fan 1, an electric heater 2, a heat regenerator 3, a heat exchanger 4, a dust remover 5, a regulating valve, a safety valve, a pipeline and the like, and the heat exchanger 4 of the main loop is currently designed as a shell-and-tube heat exchanger. Under normal working conditions, the operating pressure of the helium cooling circuit is 8MPa, and the mass flow is 1.04kg ·s -1 The inlet temperature of TBM is 300 ℃, the outlet temperature is 500 ℃, and the inlet and outlet temperatures of the water-cooled heat exchanger 4 are 255 ℃ minus 70 ℃.
The experimental section is mainly divided into a first loop and a second loop, wherein the first loop comprises an inlet and an outlet, a straight pipe section, a simulated break pipeline 6 and a steam-water collecting device 8.
The second circuit includes a second circuit pipe, a second water tank 10, and a surge tank 11.
Because the inlet and outlet pipes in the experimental loop for connecting the experimental section are DN 200, the inner diameter is 168.3mm. Therefore, in order to match inlet and outlet pipes, DN 200 is also selected as an experimental section pipe, the inner diameter is 168.3mm, the outer diameter of a flange steel pipe with neck butt welding of the connecting experimental section DN 200 is 219.1mm, and the outer diameter of the steel pipe is 219.1mm and the wall thickness is 25mm according to GB17395-2008 seamless steel pipe size, shape, weight and allowable deviation. According to the calculation of the minimum wall thickness of a straight pipe subjected to internal pressure in GB/T32270-2015 pressure pipeline standard power pipeline 6.3.2.1 and the description of allowable stress of a high alloy steel pipe in GB 150.2-2011.
The wall thickness is determined according to the inner diameter of the pipe as follows:
the allowable stress is introduced into the experimental section pipe material which can meet the design pressure of 15MPa and the design temperature of 625 ℃ and has the wall thickness, and 0Cr17Ni12Mo2 (316 stainless steel) is recommended.
Initially selecting a straight broken pipe section with the length of 4000mm as a model for simulating a first loop broken experimental section, and simulating a broken size range of 0.153cm according to actual demand conditions 2 ～15.3cm 2 Initially selecting 5 break sizes to design accident break, wherein the break area sizes are respectively 0.153cm 2 ，0.306cm2，1.53cm 2 ，7.65cm 2 ，15.3cm 2 A round tube is initially selected as the simulated break pipeline 6, and 5 break diameters are respectively 4.4mm, 6.2mm, 14.0mm, 31.2mm and 44.1mm through calculation. Each simulated break will be spaced apart Distance (preliminary interval 550 mm) to meet the aperture requirements and conditions for mounting control and measuring instruments.
Considering that the first three break sizes are very close to the last two large break sizes and the subsequent break simulation experiments with different sizes are performed, the five pipelines all adopt DN 65 pipes as simulated break pipelines 6, and each pipeline is provided with a temperature and pressure measuring point, a second venturi flowmeter 620 and a pneumatic stop valve 630 in sequence. The simulated break pipe 6 is shown in figure 2. The flange connection can also be replaced by a bayonet connection. The clamping sleeve connection has the advantages that a gasket is not required to be added, welding is not required, and the repeated assembly and disassembly performance is good and the sealing performance is also good.
And a flange connection is made at the end of each pipeline, so that the subsequent replacement of the break with different size areas is facilitated. The flange is welded with a custom pipe of a size meeting the spraying requirements, and the design of the flange connection spraying break is shown in figure 6. The flange before the simulated break can be selected from a high-pressure necked flange, a clamping sleeve or a self-tightening flange.
The second loop operating pressure is 1MPa, and considering that the upstream helium cooling loop operating pressure reaches 8MPa or even 12MPa, the spraying at the pipeline break is calculated to be critical spraying, and from the viewpoint of experimental safety, the design pressure of the second loop is 5MPa, and the design temperature is 200 ℃. Although the second loop pipeline is filled with circulating water, the high-temperature and high-pressure helium gas of the first loop can be sprayed into the second loop pipeline in consideration of the fact that the simulated break pipeline 6 is opened, and the outer diameter size of the second loop pipeline is consistent with that of the first loop pipeline, namely, the outer diameter size of the steel pipe is 219.1mm. However, since the sparge is a critical sparge and there is cooling of the water, the second loop material is selected 304 stainless steel.
According to the description of allowable stress of the high alloy steel pipe in GB 150.2-2011, the allowable stress at the design temperature is 130MPa. Calculation of minimum wall thickness of straight pipe subjected to internal pressure according to GB/T32270-2015 pressure pipeline Specification Power pipeline 6.3.2.1
The additional thickness C is 2mm, and the wall thickness of the stainless steel tube in GB17395-2008 seamless steel tube size, appearance, weight and allowable deviation is 6.5mm. The material of the second loop pipeline is 304 stainless steel, the size of the steel pipe is 219.1mm in outer diameter, and the wall thickness is 6.5mm.
The steel plate number of the second water tank and the cylinder body of the pressure stabilizing tank 11 is S30508, and the allowable stress of the high alloy steel forging is described in GB 150.2-2011. The nominal diameter of the second water tank and the cylinder body of the surge tank 11 is DN1500, and the inner diameter is 1500mm. Then according to the calculation formula of the wall thickness of the cylinder under internal pressure in GB 150.3-2011
Substituting each numerical value into the calculated wall thickness of 29.412mm, considering the corrosion allowance of 1mm and the negative deviation of the steel plate, and increasing the safety margin to confirm that the wall thickness of 32mm meets the requirement. The end enclosure adopts a standard elliptic end enclosure with the ratio of the length to the short axis of 2, as shown in figure 8, the Di is 1500mm and h i 375mm, and the straight edge length of the end socket is 25mm. Thickness formula calculated by seal head
Substituting the numerical value into the calculation formula to obtain delta h 29.126mm, to maintain consistency with the barrel thickness, the final wall thickness was 32mm.
Upstream main circuit helium design pressure P 1 =15 MPa, design temperature T 1 =898k, volume V 1 ＝2.3m 3 Original nitrogen pressure P of surge tank 11 2 =1 MPa, temperature T 2 373K, volume V 2 Assuming that all helium gas enters the surge tank 11 of the second circuit after the extreme case blowout occurs, the mixed pressure does not exceed the design pressure p=5 MPa, the design temperature t=473K, and the volume v=v 2 。
To simplify the calculation, the following formula is used
The calculated nitrogen volume of the surge tank 11 is at least 4.869m 3 Can meet the requirement, and the bottom of the pressure stabilizing tank 11 needs water with a certain height, the temporary water height is 1m, and the total volume of the pressure stabilizing tank 11 is 6.459m after calculation 3 Can meet the requirements.
In order to facilitate the replacement of the experimental section, the experimental section is connected with the inlet and outlet pipelines by adopting a flange, and butt welding flanges are adopted according to the specified design temperature of more than 300 ℃ or the pipeline with the nominal pressure of more than or equal to PN40 in the flange, the gasket and the fastener of GB/T32270-2015 pressure pipeline standard power pipeline 6.2.9. And determining that the flange connection of the inlet and the outlet of the experimental section adopts PN100 and the flange (WN) connection of the PN 160 steel pipe with neck and welded steel pipe according to the design parameters of the experimental section and the conditions of meeting the operating pressure of 8MPa and 12MPa by inquiring the standard file of HGT 20592-20635-2009 steel pipe flange, gasket and fastener, wherein the flange connection size is DN200. The flange of experimental section mainly includes: pneumatic shut-off valve flange, flow meter flange, and breach simulation flange 610. The flange proposal of the first two parts adopts a high-pressure necked flange, can be matched with a stop valve and a self-contained flange piece of the flowmeter, and the flange before the simulated break can adopt a self-tightening flange. And according to the pressure and temperature proposal, a full-thread stud and a type II hexagonal nut (304 materials are adopted). And selecting concave-convex surface sealing according to the pressure grade and the flange sealing form suitable for the winding gasket with the inner ring. Flange material: through repeated checking, and combining experience accumulated in early experiments and research and analysis results of related factories, the 12Cr1MoVG (12 chromium molybdenum vanadium steel) material meets the design temperature and pressure requirements.
And selecting a basis by the first loop pipeline flange, and selecting a PN63 neck butt welding flange by the second loop pipeline flange according to the design pressure and the design temperature of the second loop.
The connection of instruments and meters of the simulated break pipeline 6 is recommended to adopt flange connection of a neck butt welding steel pipe, the flange material type number is 1C14 (chromium molybdenum chromium steel), the sealing surface is in the form of concave-convex surface, the sealing element is required to adopt M24 full-thread studs and II hexagonal nuts (the materials are 304), and the gasket is selected to be a winding gasket (the metal belt material is 304L and the filling material is flexible graphite tape). And selecting a flange with a neck and welded steel tube of DN65 according to the nominal diameter of the pipeline.
Second loop water enters the first loop helium cooling system process test scheme:
in order to simulate the pipe rupture accident of the heat exchanger, the experimental section is divided into a first circuit (helium cooling system) and a second circuit (secondary side water circuit), and 7.65cm of the designed break size is considered 2 ，15.3cm 2 The large break is large in helium leakage amount when an accident occurs, so that an isolation valve is additionally arranged at the water side inlet and outlet of the secondary side water loop, namely the water side inlet and outlet of the heat exchanger 4, and the isolation valve has short response time.
The valve on the simulated break pipeline 6 is opened for simulating the pipeline breakage of the heat exchanger, and the inlet and outlet valves of the first circuit are closed to simulate triggering of a shutdown signal, high-pressure helium gas in the first circuit, namely a helium cooling system, after the pipeline breakage (after an accident) enters a second circuit, namely a secondary side water circuit through the simulated break pipeline 6, the pressure in the first circuit is reduced, the pressure in the second circuit is increased along with the reduction, when the pressure in the second circuit is greater than or equal to the pressure in the first circuit, water in the second circuit enters the helium cooling system of the first circuit through the simulated break pipeline 6, at the moment, high-temperature high-pressure helium gas in the first circuit can enable water to be gasified into steam and entrained in the helium gas, and in order to test the process that the secondary side water flows backwards into the first circuit after the accident, a steam-water collecting device 8 shown in figure 3 is designed in the first circuit for detecting the water quantity entering the first circuit.
Under normal working conditions of the experimental section, the valves at the two ends of the first isolation valve 830 and the second water tank 10 are opened, and the valves on the second isolation valve 850, the third isolation valve 860 and the simulated break pipeline 6 are closed. After the pipeline breaks (after an accident occurs), the valves at the inlet and outlet of the first loop, the first isolation valve 830 and the two ends of the second water tank 10 are closed, the valves on the second isolation valve 850, the third isolation valve 860 and the simulated break pipeline 6 are opened, water vapor entrained in helium gas enters the spiral pipe in the first water tank 820, and cooling water flowing in the first water tank 820 forcibly cools the spiral pipe to condense steam in the helium gas into condensed water.
The present embodiment adopts a sampling weighing method to determine the water quality entering the first loop, a sampling hole is formed in the sampling point of the spiral pipe, the sampling hole is connected with the sampling pipe 840, and a needle valve is arranged on the sampling pipe 840. The valve is closed when the experiment is performed in the break simulation, after the experiment is finished, 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, and the condensed water in the spiral tube is pumped out for weighing.
Meanwhile, in order to detect the water quality entering the first loop in real time, a proper online steam-water sensor is selected to be installed on the spiral pipe for online detection of the water quality, and the weighing method can be combined, and then the online measurement can be carried out by adopting the silk screen sensor. The online steam-water sensor is used for monitoring the transient change of the steam-water content online in real time.
Regarding flow measurement, a second venturi flowmeter 620 is selected to measure flow before and after the inlet and outlet of the experimental section; the simulated break line 6 is also provided with a second venturi meter 620 to measure the flow of the helium gas after the pneumatic shut-off valve 630 and before the break is blown out. The venturi flowmeter works as shown in fig. 9, because the helium temperature is higher, the pressure difference measurement is carried out by leading the pressure guiding pipe into the water tank for cooling and then connecting the pressure transmitter, so that the flow measurement is carried out. The accuracy of the second venturi meter 620 is not affected in the range, and geometric dimensions such as the throttling size of the venturi tube are determined according to the flow and the pipeline size during the design and manufacture of the meter.
Critical flow is a phenomenon in which the flow rate reaches a maximum at a given upstream condition, which occurs in both single and two phases. Critical flow studies have become quite clear for single phase fluids, typically occurring where the flow velocity at the smallest cross section reaches the speed of sound. In the experimental section loop, critical flow can be achieved only in the break spraying section, so that the break spraying flow is needed to be obtained to determine the type of the flowmeter. The outlet size, namely the break size, is 0.153cm 2 、0.306cm 2 、1.53cm 2 、7.65cm 2 、15.3cm 2 Substituting into a critical flow calculation formula, and calculating to obtain the critical flow of 0.026kg/s, 0.0519kg/s, 0.2597kg/s, 1.2983kg/s and 2.5965kg/s respectively.
Regarding temperature measurement, temperature measuring points are arranged before the inlet of the experimental section, after the outlet of the experimental section, before helium spraying of the simulated break pipeline 6, before the second loop pipeline and the water tank, and are used for monitoring the system temperature of the experimental section. In the embodiment, a K-type thermocouple is adopted for temperature measurement, and the maximum measuring range is 800 ℃ and the I-level precision is achieved. And a sealing joint with high temperature resistance and high pressure resistance is designed at the opening of the temperature measuring point on the pipeline.
Regarding the pressure measurement, pressure measuring points for monitoring the pressures of the first circuit and the second circuit are arranged before the inlet and after the outlet of the experimental section, before helium spraying of the simulated break pipeline 6, before the second circuit pipeline, the water tank and the surge tank 11. The pressure measurement of the first loop also suggests that the pressure guiding pipe is used for guiding the heat exchange water tank to cool and then is connected with the pressure transmitter for pressure measurement, and the EJA440A high pressure transmitter can be adopted as the design pressure of the experimental system is 15MPa at most, the measuring range is-0.1-32 MPa, and the accuracy is +/-0.12%. And a sealing joint with high temperature resistance and high pressure resistance is designed at the opening of the pressure measuring point on the pipeline.
The foregoing detailed description of the invention has been presented for purposes of illustration and description, and it should be understood that the invention is not limited to the particular embodiments disclosed, but is intended to cover all modifications, equivalents, alternatives, and improvements within the spirit and principles of the invention.
Claims (10)
1. A heat exchanger break simulation subassembly for fusion reactor helium cold cladding cooling system, characterized in that includes:
the device comprises a simulated break pipeline, a first pipeline and a second pipeline, wherein one end of the simulated break pipeline is used for being communicated with a helium gas conveying pipeline, the other end of the simulated break pipeline is used for being communicated with a secondary side water conveying pipeline, and a valve for controlling the opening and closing of the simulated break pipeline is arranged on the simulated break pipeline; and
the steam-water collecting device is arranged on the helium gas conveying pipeline and is positioned at the downstream of the joint of the simulated break pipeline and the helium gas conveying pipeline;
the soda water collecting device comprises:
the bent pipe is arranged on the helium gas conveying pipeline as a bypass, the inlet and the outlet of the bent pipe are provided with valves, at least one part of the bent pipe is bent downwards along the gravity direction, and the lower part of the bent part is communicated with a sampling pipe for guiding out liquid in the pipe;
a first tank in which the curved pipe is disposed;
the first isolation valve is used for being arranged on the helium gas conveying pipeline, and two ends, connected with the helium gas conveying pipeline, of the bent pipe are respectively located at the front end and the rear end of the first isolation valve.
2. A heat exchanger break simulation assembly for a fusion reactor helium cold blanket cooling system according to claim 1, wherein,
The curved pipe is a spiral pipe which is transversely arranged, and the bottom of the spiral pipe in the gravity direction is provided with the sampling pipe for guiding out cooled water.
3. A heat exchanger break simulation assembly for a fusion reactor helium cold blanket cooling system according to claim 2, wherein,
the steam-water collecting device further comprises an online steam-water sensor arranged in the spiral pipe and used for online monitoring of steam-water content in the sampled gas.
4. Heat exchanger crack experimental system of fusion reactor helium cold cladding cooling system, which is characterized in that includes:
a first circuit comprising a line for delivering helium;
a second circuit comprising a pipe for transporting water;
the device comprises a simulated break pipeline, a first loop and a second loop, wherein one end of the simulated break pipeline is communicated with the first loop, the other end of the simulated break pipeline is communicated with the second loop, and a valve for controlling the simulated break pipeline to be opened and closed is arranged on the simulated break pipeline;
the vapor-water collecting device is arranged on the helium gas conveying pipeline;
the simulated break pipelines are arranged in a plurality, and in the simulated break pipelines, the diameter of each or part of the simulated break pipelines is different or the diameter of part of the simulated break pipelines is different;
the steam-water collecting device is arranged at the downstream of the joint of the simulated break pipeline and the first loop;
The soda water collecting device comprises:
the bent pipe is arranged on the helium gas conveying pipeline as a bypass, the inlet and the outlet of the bent pipe are provided with valves, at least one part of the bent pipe is bent downwards along the gravity direction, and the lower part of the bent part is communicated with a sampling pipe for guiding out liquid in the pipe;
a first tank in which the curved pipe is disposed;
the first isolation valve is used for being arranged on the helium gas conveying pipeline, and two ends, connected with the helium gas conveying pipeline, of the bent pipe are respectively located at the front end and the rear end of the first isolation valve.
5. The heat exchanger break experiment system of the fusion reactor helium cold cladding cooling system according to claim 4, wherein,
the first loop comprises a high-pressure helium pipe conveying pipe, and an inlet and an outlet of the high-pressure helium pipe conveying pipe are respectively connected with a venturi flowmeter;
and a venturi flowmeter is arranged on the simulated break pipeline and is positioned at the upstream of the valve on the simulated break pipeline.
6. The heat exchanger break experiment system of the fusion reactor helium cold cladding cooling system according to claim 5, wherein,
the inlet and outlet two ends of the curved pipe are communicated with the high-pressure helium pipe conveying pipe, and a first isolation valve arranged on the high-pressure helium pipe conveying pipe is arranged between the two parts of the curved pipe, which are communicated with the high-pressure helium pipe conveying pipe.
7. The heat exchanger break experiment system of the fusion reactor helium cold cladding cooling system according to claim 6, wherein,
the curved pipe is a spiral pipe which is transversely arranged, and the bottom of the spiral pipe in the gravity direction is provided with the sampling pipe for guiding out cooled water.
8. The heat exchanger break experiment system of the fusion reactor helium cold cladding cooling system according to claim 4, wherein,
a stop valve is further arranged on the simulated break pipeline, and a break simulation flange is arranged on one side, close to the second loop, of the stop valve along the direction of helium flowing to the second loop;
among the plurality of simulated break lines, the break simulation flanges of the simulated break lines have different diameters of outlets on a side of the simulated flange that is adjacent to the second circuit.
9. The heat exchanger break experiment system of the fusion reactor helium cold cladding cooling system according to claim 4, wherein,
the second circuit includes:
an aqueous medium delivery line;
the two ends of the water medium conveying pipeline are communicated with the second water tank; the water medium conveying pipeline is connected with the first loop through a simulated break pipeline;
and the pressure stabilizing tank is communicated with the second water tank.
10. A method for simulating cracking of a heat exchanger tube, characterized in that a heat exchanger cracking test system of a fusion reactor helium cold blanket cooling system according to any one of claims 4 to 9 is employed, said method for simulating cracking of a heat exchanger tube comprising the steps of:
closing a first loop inlet and outlet valve for simulating and triggering a shutdown signal;
after helium enters the second loop from the simulated break pipeline;
when the pressure of the second loop is higher than a preset pressure test limit value on the second loop or the pressure of the first loop is lower than a preset pressure test limit value on the first loop, starting a first loop inlet and outlet valve closing response signal;
the inlet and outlet valves of the first loop are completely closed according to preset closing time, when the pressure of the first loop and the pressure of the second loop reach balance, and when the flow measured by the flow meter of the simulated break pipeline changes to zero, the experiment is ended, experimental data are collected, the valve of the simulated break pipeline is closed, and the mass of helium entering the second loop is measured by detecting the liquid level information in the pressure stabilizing tank of the second loop and the pressure temperature information of the second loop;
when the pressure of the second loop is greater than or equal to the pressure in the first loop, closing a first isolation valve on the first loop, and opening a second isolation valve, a third isolation valve and a valve on a simulated break pipeline to enable water vapor entrained in helium to enter a spiral pipe in a first water tank, wherein cooling water flowing in the first water tank forcibly cools the spiral pipe to enable the vapor in the helium to be condensed into condensed water;
The online steam-water detection equipment is used for detecting the steam-water content in the real-time helium, after the valve of the simulated break pipeline and the first isolation valve are closed, the spiral pipe and the main loop pipeline are cooled to normal temperature in a static mode, at the moment, the valve of the sampling pipe is opened, and all water collected in the spiral pipe is discharged and weighed, so that the water quality of the helium entering the first loop system from the second loop in an accident experiment is obtained.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN202310363620.0A CN116403743A (en) | 2023-04-06 | 2023-04-06 | Heat exchanger break simulation system and method for fusion reactor helium cold cladding cooling system |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202310363620.0A CN116403743A (en) | 2023-04-06 | 2023-04-06 | Heat exchanger break simulation system and method for fusion reactor helium cold cladding cooling system |
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| CN116403743A true CN116403743A (en) | 2023-07-07 |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN117133494A (en) * | 2023-07-19 | 2023-11-28 | 华能核能技术研究院有限公司 | Helium quick recovery and reuse device |
| CN117133494B (en) * | 2023-07-19 | 2024-06-04 | 华能核能技术研究院有限公司 | Helium quick recovery and reuse device |
-
2023
- 2023-04-06 CN CN202310363620.0A patent/CN116403743A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN117133494A (en) * | 2023-07-19 | 2023-11-28 | 华能核能技术研究院有限公司 | Helium quick recovery and reuse device |
| CN117133494B (en) * | 2023-07-19 | 2024-06-04 | 华能核能技术研究院有限公司 | Helium quick recovery and reuse device |
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