Fusion reactor water cooling cladding first wall flow instability experiment device and experiment method

Abstract

The invention discloses an experimental device and an experimental method for flow instability of a first wall of a water-cooled cladding of a fusion reactor. The experimental device comprises an experimental section, an inlet header, an outlet header and a connecting pipe group, the connecting pipe group comprises a plurality of connecting pipes; the experiment section comprises an experiment section main body, and a first channel and a second channel are arranged in the experiment section main body; the inlet header comprises an inlet header body and at least two inlet header connecting pipes; the two inlet header connecting pipes are respectively communicated with the first channel and the second channel; the outlet header comprises an outlet header body and at least two outlet header connecting pipes; the outlet header connecting pipes are respectively communicated with the first channel and the second channel; and the experiment section main body, the inlet header and the outlet header are communicated through the connecting pipe group to form two runner passages. By adopting the two-channel slice model, the structural characteristics of the first wall of the water-cooled cladding of the fusion reactor are reserved to the greatest extent, the flow instability characteristic of the first wall is well reflected, and the experiment cost is reduced.

Description

Technical Field

[0001] The invention relates to an experimental device, in particular to a fusion reactor water-cooled blanket first wall flow instability experimental device and an experimental method. Background Art

[0002] As an important component in a nuclear fusion reactor that is directly exposed to high-temperature plasma, the first wall must withstand high heat flux density, high-pressure working fluid, and complex thermal stresses caused by temperature gradients and thermal expansion. These harsh working conditions require that the first wall not only have excellent cooling capabilities to quickly dissipate heat and maintain material integrity, but also have sufficient structural strength to cope with the various complex mechanical stresses generated during operation. Therefore, the water-cooled ceramic breeder blanket of the Fusion Engineering Test Reactor uses square parallel channels as the cooling structure of the first wall. Taking the equatorial outer blanket module as an example, its first wall consists of 95 parallel square channels. However, the complexity of the two-phase flow in the parallel channel will not only lead to overall flow instability, but also some instability phenomena unique to the parallel channel will occur due to the interaction between the pipes, which will cause continuous oscillations, thereby reducing the operating performance of the equipment and the safety of the system.

[0003] Most of the existing experimental devices for flow instability are derived from the research on steam generators, so the designed experimental sections usually have the following characteristics: 1. The channel is a circular channel; 2. The circular tube channel is used as a heat source to provide a circumferentially uniform heat flow for the experimental section; 3. The experimental channels are independent and do not contact each other, and there is no heat exchange between the channels; 4. The working fluid flows in the two channels in the same direction. However, these characteristics deviate from the cooling design of the first wall of the fusion reactor water-cooled blanket, and the experimental data obtained through these experimental devices cannot reflect the flow instability characteristics of the first wall of the fusion reactor water-cooled blanket.

[0004] Therefore, a flow instability experimental device suitable for the first wall of the water-cooled blanket of a fusion reactor is needed. Summary of the invention

[0005] In order to solve the above-mentioned technical problems, the present invention provides a flow instability experimental device for the first wall of the water-cooled blanket of a fusion reactor. The flow instability experimental device for the first wall of the water-cooled blanket of a fusion reactor of the present invention retains the key characteristics and structure of the first wall of the water-cooled blanket of a fusion reactor, simplifies the experimental cost, and realizes the low-cost acquisition of experimental data with practical value.

[0006] Correspondingly, the present invention also provides a fusion reactor water-cooled blanket first wall flow instability test method using the above-mentioned fusion reactor water-cooled blanket first wall flow instability test device.

[0007] A fusion reactor water-cooled blanket first wall flow instability experimental device, the experimental device comprising: an experimental section, an inlet header, an outlet header and a connecting pipe group; the experimental section, the inlet header and the outlet header are connected through a connecting pipe group; the connecting pipe group comprises a plurality of connecting pipes;

[0008] The experimental section includes an experimental section body, and a first channel and a second channel are arranged inside the experimental section body; the inlet manifold includes an inlet manifold body and at least two inlet manifold pipes; the two inlet manifold pipes are respectively connected to the first channel and the second channel; the outlet manifold includes an outlet manifold body and at least two outlet manifold pipes, and the outlet manifold pipes are respectively connected to the first channel and the second channel; the experimental section body, the inlet manifold and the outlet manifold are connected through a connecting pipe group to form two flow passages.

[0009] Wherein, the two inlet header pipes are arranged on both sides of the inlet header body; the two outlet header pipes are arranged on both sides of the outlet header body;

[0010] And / or, the two inlet header pipes are arranged on one side of the inlet header body; the two outlet header pipes are arranged on one side of the outlet header body.

[0011] There are three inlet header pipes, two of which are arranged on one side of the inlet header body, and the other inlet header pipe is arranged on the other side of the inlet header body;

[0012] There are three outlet header pipes, two of which are arranged on one side of the outlet header body, and the other outlet header pipe is arranged on the other side of the outlet header body.

[0013] There are four inlet header pipes, two of which are arranged on one side of the inlet header body, and the other two inlet header pipes are arranged on the other side of the inlet header body;

[0014] There are four outlet manifold pipes, two of which are arranged on one side of the outlet manifold body, and the other two outlet manifold pipes are arranged on the other side of the outlet manifold body.

[0015] The fusion reactor water-cooled blanket first wall flow instability experimental device further comprises a plug for closing an outlet header pipe or an inlet header pipe.

[0016] Wherein, a heating component is arranged on a side of the experimental section body facing the plasma.

[0017] Wherein, the first channel and the second channel are both square channels.

[0018] The first channel and the second channel are processed on the same piece of material, and the two channels realize heat exchange through a common wall surface.

[0019] Wherein, a plurality of measuring point sections are non-uniformly arranged on the main body of the experimental section, and a plurality of temperature measuring points are arranged on each of the measuring point sections;

[0020] And / or, measuring points for the working fluid are provided at the entrance and exit of the experimental device and the entrance and exit of the experimental section.

[0021] An experimental method for flow instability of the first wall of a fusion reactor water-cooled blanket is provided, using the above-mentioned experimental device. The experimental method comprises the following steps:

[0022] Connect the corresponding pipelines of the experimental device according to the actual working conditions to make them consistent with the actual working conditions;

[0023] Determine the operating parameters of the experimental device according to the actual working conditions, so that the working fluid in the experimental device flows according to the operating parameters;

[0024] Monitor the corresponding parameters of the working fluid at the outlet of the experimental section until the corresponding parameters are stable;

[0025] Continuously increase the power of the heating component in predetermined steps until the corresponding parameters are stable;

[0026] When the medium flow at the outlet of the experimental section oscillates, the power applied to the heating component is the critical power of flow instability.

[0027] The beneficial effects of the present invention are:

[0028] (1) The present invention uses two channel slices as experimental sections, which significantly reduces the experimental cost and obtains acceptable experimental data credibility. The two-channel design is used to simulate the first wall prototype. The simulation study found that the deviation between the experimental section results of the two channels and the results of the first wall prototype is less than 6.5%. The two-channel slice model retains the structural characteristics of the first wall of the fusion reactor water-cooled blanket to the greatest extent, and the experimental data can well reflect the flow instability characteristics of the first wall; at the same time, the experimental cost is simplified.

[0029] (2) The heating component is used as a single heat source and is melted onto the single-side surface of the test section. Compared with the existing flow instability experimental device, it provides the test section with a single-side heat flow that is the same as the first wall of the fusion reactor prototype.

[0030] (3) A square channel is used as the cooling channel. Compared with the existing flow instability experimental device, it retains the same structural features as the cooling channel of the first wall prototype of the fusion reactor.

[0031] (4) The two channels are processed on the same piece of material, and there is no isolation between the channels. Compared with the existing flow instability experimental device, the characteristic of heat exchange between the first wall channels of the fusion reactor is retained.

[0032] (5) The experimental device can quickly switch between the countercurrent and cocurrent states of the two flow channels in the experimental section by replacing the connecting pipe group, thus expanding the application scope of the experimental device. BRIEF DESCRIPTION OF THE DRAWINGS

[0033] Figure 1 This is an exploded view of the first wall flow instability experimental device of the fusion reactor water-cooled blanket of the present invention.

[0034] Figure 2 It is a cross-sectional schematic diagram of the test section measuring points of the fusion reactor water-cooled blanket first wall flow instability experimental device of the present invention.

[0035] Figure 3 The present invention is a process flow chart of the first wall flow instability experimental device of the fusion reactor water-cooled blanket.

[0036] Among them: 1-the main body of the experimental section; 11-the first experimental section take-over; 12-the second experimental section take-over; 13-the third experimental section take-over; 14-the fourth experimental section take-over; 2-the inlet manifold body; 20-the inlet manifold inlet; 21-the first inlet manifold take-over; 22-the second inlet manifold take-over; 23-the third inlet manifold take-over; 24-the fourth inlet manifold take-over; 3-the outlet manifold body; 30-the outlet manifold outlet; 31-the first outlet manifold take-over; 32-the second outlet manifold take-over; 33-the third outlet manifold take-over; 34-the fourth outlet manifold take-over; 4-the heating component; 5-the connecting pipe group; 6-the plug. DETAILED DESCRIPTION

[0037] In order to make the purpose, technical solutions and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present invention and are not intended to limit the present invention. In addition, the technical features involved in the various embodiments of the present invention described below can be combined with each other as long as they do not conflict with each other.

[0038] See also Figure 1 The present invention provides a fusion reactor water-cooled blanket first wall flow instability experimental device, the experimental device comprises: an experimental section, an inlet header, an outlet header and a connecting pipe group 5; the experimental section, the inlet header and the outlet header are connected through a connecting pipe group; the connecting pipe group comprises a plurality of connecting pipes;

[0039] The experimental section includes an experimental section body 1, and the experimental section body 1 is provided with a first channel and a second channel (not shown in the figure); the inlet manifold includes an inlet manifold body 2 and at least two inlet manifold pipes; the two inlet manifold pipes are connected to the first channel and the second channel respectively; the outlet manifold includes an outlet manifold body 3 and at least two outlet manifold pipes, and the outlet manifold pipes are connected to the first channel and the second channel respectively; the experimental section body, the inlet manifold and the outlet manifold are connected through a connecting pipe group to form two flow passages. The first channel and the second channel are arranged inside the experimental section body 1, and the two ends of the first channel are connected to the first experimental section pipe 11 and the fourth experimental section pipe 14 respectively, and the first channel is connected to the connecting pipe through the first experimental section pipe 11 and the fourth experimental section pipe 14; the two ends of the second channel are connected to the second experimental section pipe 12 and the third experimental section pipe 13 respectively, and the second channel is connected to the connecting pipe through the second experimental section pipe 12 and the third experimental section pipe 13.

[0040] The first wall of the water-cooled blanket of a fusion reactor is usually composed of dozens of square parallel channels. If the experiment is carried out directly with the prototype, the cost is huge and the current heating technology cannot provide a sufficiently high heat flux for the experimental piece. Considering that the first wall channel is a multiple repetition of the square channel in the polar direction, the most representative two-channel slice model is extracted as the experimental section. The present invention uses two channels (the first channel and the second channel) as the experimental section, which significantly reduces the experimental cost and obtains acceptable experimental data credibility. The two-channel design is used to simulate the first wall prototype. The simulation study found that the deviation between the experimental section results of the two channels and the results of the first wall prototype is less than 6.5%. The two-channel slice model retains the structural characteristics of the first wall of the water-cooled blanket of the fusion reactor to the greatest extent, and the experimental data can well reflect the flow instability characteristics of the first wall; at the same time, it simplifies the experimental cost.

[0041] In one embodiment, the two inlet manifold pipes are arranged on both sides of the inlet manifold body; the two outlet manifold pipes are arranged on both sides of the outlet manifold body. In this embodiment, the working fluid flows in the two channels of the experimental section body 1 in opposite directions. Figure 1, the two inlet header pipes are the first inlet header pipe 21 (or the second inlet header pipe 22) on the left and the third inlet header pipe 23 (or the fourth inlet header pipe 24) on the right, and the two outlet header pipes are the first outlet header pipe 31 (or the second outlet header pipe 32) on the left and the third outlet header pipe 33 (or the fourth outlet header pipe 34) on the right. At this time, the first inlet header pipe 21 (or the second inlet header pipe 22) on the left, the first channel and the third outlet header pipe 33 (or the fourth outlet header pipe 34) on the right form a first flow passage; the third inlet header pipe 23 (or the fourth inlet header pipe 24) on the right, the second channel and the first outlet header pipe 31 (or the second outlet header pipe 32) on the left form a second flow passage.

[0042] In another embodiment, the two inlet manifold pipes are arranged on one side of the inlet manifold body; the two outlet manifold pipes are arranged on one side of the outlet manifold body. In this embodiment, the working fluid flows in the two channels of the experimental section 1 in the same direction. Figure 1 , the two inlet manifold pipes are the first inlet manifold pipe 21 and the second inlet manifold pipe 22 located on the left, and the two outlet manifold pipes are the third outlet manifold pipe 33 and the fourth outlet manifold pipe 34 located on the right. At this time, the first inlet manifold pipe 21 on the left, the first channel and the third outlet manifold pipe 33 or the fourth outlet manifold pipe 34 on the right form a first flow passage; the second inlet manifold pipe 22 on the left, the second channel and the third outlet manifold pipe 33 or the fourth outlet manifold pipe 34 on the right form a second flow passage. Alternatively, the two inlet manifold pipes are the third inlet manifold pipe 23 and the fourth inlet manifold pipe 24 located on the right, and the two outlet manifold pipes are the first outlet manifold pipe 31 and the second outlet manifold pipe 32 located on the left. At this time, the third inlet manifold pipe 23 on the right, the first channel and the first outlet manifold pipe 31 or the second outlet manifold pipe 32 on the left form a first flow passage; the fourth inlet manifold pipe 24 on the right, the second channel and the first outlet manifold pipe 31 or the second outlet manifold pipe 32 on the left form a second flow passage.

[0043] Furthermore, there are three inlet manifold pipes, two of which are arranged on one side of the inlet manifold body, and the other is arranged on the other side of the inlet manifold body; there are three outlet manifold pipes, two of which are arranged on one side of the outlet manifold body, and the other is arranged on the other side of the outlet manifold body. The experimental device in this embodiment can realize the switching of the two states of downstream and upstream. It is only necessary to connect the corresponding inlet manifold pipe and outlet manifold pipe to the first channel or the second channel.

[0044] More preferably, in this embodiment, there are four inlet header pipes, two of which are arranged on one side of the inlet header body, and the other two are arranged on the other side of the inlet header body; there are four outlet header pipes, two of which are arranged on one side of the outlet header body, and the other two are arranged on the other side of the outlet header body. Figure 1 There are four inlet manifold pipes, namely, the first inlet manifold pipe 21, the second inlet manifold pipe 22, the third inlet manifold pipe 23 and the fourth inlet manifold pipe 24. The first inlet manifold pipe 21 and the second inlet manifold pipe 22 are located on one side of the inlet manifold body 2, and the third inlet manifold pipe 23 and the fourth inlet manifold pipe 24 are located on the other side of the inlet manifold body 2; there are four outlet manifold pipes, namely, the first outlet manifold pipe 31, the second outlet manifold pipe 32, the third outlet manifold pipe 33 and the fourth outlet manifold pipe 34. The first outlet manifold pipe 31 and the second outlet manifold pipe 32 are located on one side of the outlet manifold body 3, and the third outlet manifold pipe 33 and the fourth outlet manifold pipe 34 are located on the other side of the outlet manifold body 3. By replacing the connecting pipe group, the two flow channels of the experimental section can be quickly switched between the countercurrent and downstream states, which expands the application range of the experimental device.

[0045] As an embodiment, cooling water (working fluid) from the upstream of the experimental system enters the inlet manifold body 2 through the inlet manifold inlet 20, and flows into the experimental section from the first inlet manifold pipe 21 and the third inlet manifold pipe 23 through the connecting pipe group 5, the first experimental section pipe 11 and the third experimental section pipe 13 respectively, and then flows into the outlet manifold body 3 from the second experimental section pipe 12 and the fourth experimental section pipe 14 through the connecting pipe group 5, the second outlet manifold pipe 32 and the fourth outlet manifold pipe 34 respectively and merges, and finally flows into the downstream of the experimental system through the outlet manifold outlet 30.

[0046] For better, see Figure 1 When there are more than two inlet header pipes or more than two outlet header pipes, a plug 6 can be used to close the outlet header pipe or the inlet header pipe that is not used temporarily. The plug 6 is threadedly connected to the inlet header pipe and the outlet header pipe.

[0047] The test section pipes, connecting pipe groups, inlet header pipes and outlet header pipes are welded by argon arc welding.

[0048] For better, see Figure 1A heating component 4 is provided on the outer wall of the experimental section body 1 facing the plasma. The heating component in this embodiment is an electric heating film. The electric heating film is used as a single heat source and is melted on the single-side surface of the experimental section. Compared with the existing flow instability experimental device, the experimental section is provided with the same heat flow characteristics as the first wall of the fusion reactor first wall prototype. The electric heating film is melted on the surface of the experimental section body 1. The electric heating film is melted on the plasma-facing side of the experimental section and is the only heat source of the experimental section, providing a single-direction heat flow for the experimental section. The first wall of the water-cooled blanket of a fusion reactor mainly bears high-density heat flow from high-temperature plasma. Due to the structural characteristics of the fusion reactor, the high heat flow only exists on the side of the first wall facing the plasma, so the first wall bears a single-sided high heat flow. The flow instability experimental device for the first wall of the water-cooled blanket of a fusion reactor of the present invention uses an electric heating film as a heat source, which is only melted on the plasma-facing side of the experimental section, providing the experimental section with a heat flow condition that conforms to the first wall prototype.

[0049] Preferably, the first channel and the second channel are both square channels. The square channel is used as the cooling channel, and compared with the existing flow instability experimental device, the same structural features as the cooling channel of the first wall prototype of the fusion reactor are retained. Its size is consistent with the channel structure size of the first wall of the actual fusion reactor.

[0050] Preferably, the first channel and the second channel are processed on the same piece of material, and the coolants in the two channels achieve heat exchange through the shared wall surface. Compared with the existing flow instability experimental device, the characteristic of heat exchange between the first wall channels of the fusion reactor is retained.

[0051] In one embodiment, considering that the temperature distribution of the experimental section channel satisfies the central symmetry, in order to obtain more data at the minimum cost, a plurality of measuring point sections are non-uniformly arranged on the experimental section body 1, and a plurality of temperature measuring points are arranged on each measuring point section. Figure 2 In this embodiment, the end of the left curved section of the experimental section body 1 is taken as the starting point, and 8 measuring point sections are non-uniformly set, numbered A~H; each measuring point section is set with 13 temperature measuring points. Among them, one thermocouple is set for the thermocouple hole diameter of 0.6mm, two thermocouples with an axial distance of 5mm are set for the hole diameter of 1mm, and three thermocouples with an axial distance of 5mm are set for the hole diameter of 1.5mm.

[0052] Preferably, the entrance and exit of the experimental device and the entrance and exit of the experimental section are both provided with measuring points for the working fluid. The entrance and exit of the experimental device and the entrance and exit of the experimental section body 1 are both provided with measuring points for the working fluid. Figure 1The working fluid pressure, temperature, and flow rate were measured at the inlet 20 of the inlet manifold, the working fluid pressure and temperature were measured at the outlet 30 of the outlet manifold, the working fluid pressure, temperature, and flow rate were measured at the first experimental section pipe 11 and the third experimental section pipe 13, and the pressure difference between the outlet and inlet of each channel of the experimental section was measured.

[0053] The present invention also provides an experimental method for flow instability of the first wall of a fusion reactor water-cooled blanket, comprising the following steps:

[0054] Connect the corresponding pipelines of the experimental device according to the actual working conditions to make them consistent with the actual working conditions;

[0055] Determine the operating parameters of the experimental device according to the actual working conditions, so that the working fluid in the experimental device flows according to the operating parameters;

[0056] Monitor the corresponding parameters of the working fluid at the outlet of the experimental section until the corresponding parameters are stable; the corresponding parameters include pressure, temperature and flow rate;

[0057] Continuously increase the power of the heating component in a predetermined step size until the corresponding parameters are stable; the predetermined step size is determined according to actual needs;

[0058] When the medium flow at the outlet of the experimental section oscillates, the power applied to the heating component is the critical power of flow instability. The flow instability boundary of the first wall of the water-cooled ceramic breeder blanket of the China Fusion Engineering Test Reactor will be obtained through conversion.

[0059] For details, see Figure 3 During the experiment, the working fluid in the experimental device flows according to the operating parameters. The power of the electric heating film is increased from zero in steps of 1 kW. After each power increase, the working fluid pressure, temperature, and flow rate measured at the outlet of the experimental section main body 1 are monitored. After the working fluid parameters are stable for one minute, the power of the electric heating film is increased again in one step. These steps are repeated until the medium flow at the outlet of the experimental section 1 oscillates. The power applied by the electric heating film to the experimental section main body 1 when oscillation occurs is the critical power of the flow instability of the experimental section. The flow instability boundary of the first wall of the water-cooled ceramic breeder blanket of the China Fusion Engineering Test Reactor will be obtained by conversion.

[0060] In the description of the present invention, “plurality” means at least two, for example, two, three, etc., unless otherwise clearly and specifically defined.

[0061] In the description of this specification, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" etc. means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present invention. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described may be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art may combine and combine different embodiments or examples described in this specification and features of different embodiments or examples, unless they are contradictory.

[0062] It will be easily understood by those skilled in the art that the above description is only a preferred embodiment of the present invention and is not intended to limit the present invention. Any modifications, equivalent substitutions and improvements made within the spirit and principles of the present invention should be included in the protection scope of the present invention.

[0063] The parts not elaborated in detail in the description of the present invention belong to the known technology in the art. The above embodiments are provided only for the purpose of describing the present invention, and are not intended to limit the scope of the present invention. The scope of the present invention is defined by the appended claims. Various equivalent substitutions and modifications made without departing from the spirit and principle of the present invention should be included in the scope of the present invention.

Claims

1. A fusion reactor water-cooled blanket first wall flow instability experimental device, characterized in that: The experimental device comprises: an experimental section, an inlet header, an outlet header and a connecting pipe group; the experimental section, the inlet header and the outlet header are connected through the connecting pipe group; the connecting pipe group comprises a plurality of connecting pipes; The experimental section includes an experimental section body, and a first channel and a second channel are arranged inside the experimental section body; the inlet manifold includes an inlet manifold body and at least two inlet manifold pipes; the two inlet manifold pipes are respectively connected to the first channel and the second channel; the outlet manifold includes an outlet manifold body and at least two outlet manifold pipes, and the outlet manifold pipes are respectively connected to the first channel and the second channel; the experimental section body, the inlet manifold and the outlet manifold are connected through a connecting pipe group to form two flow passages.

2. The fusion reactor water-cooled blanket first wall flow instability experimental device according to claim 1, characterized in that: The two inlet header pipes are arranged on both sides of the inlet header body; the two outlet header pipes are arranged on both sides of the outlet header body; And / or, the two inlet header pipes are arranged on one side of the inlet header body; the two outlet header pipes are arranged on one side of the outlet header body.

3. The fusion reactor water-cooled blanket first wall flow instability experimental device according to claim 1, characterized in that: There are three inlet header pipes, two of which are arranged on one side of the inlet header body, and the other inlet header pipe is arranged on the other side of the inlet header body; There are three outlet header pipes, two of which are arranged on one side of the outlet header body, and the other outlet header pipe is arranged on the other side of the outlet header body.

4. The fusion reactor water-cooled blanket first wall flow instability experimental device according to claim 1, characterized in that: There are four inlet header pipes, two of which are arranged on one side of the inlet header body, and the other two inlet header pipes are arranged on the other side of the inlet header body; There are four outlet manifold pipes, two of which are arranged on one side of the outlet manifold body, and the other two outlet manifold pipes are arranged on the other side of the outlet manifold body.

5. The fusion reactor water-cooled blanket first wall flow instability experimental device according to claim 4, characterized in that: The fusion reactor water-cooled blanket first wall flow instability experimental device also includes a plug for closing an outlet header pipe or an inlet header pipe.

6. The fusion reactor water-cooled blanket first wall flow instability experimental device according to claim 1, characterized in that: A heating component is arranged on a side of the experimental section body facing the plasma.

7. The fusion reactor water-cooled blanket first wall flow instability experimental device according to claim 1, characterized in that: The first channel and the second channel are both square channels.

8. The fusion reactor water-cooled blanket first wall flow instability experimental device according to claim 1, characterized in that: The first channel and the second channel are processed on the same piece of material, and the two channels realize heat exchange through a common wall surface.

9. The fusion reactor water-cooled blanket first wall flow instability experimental device according to any one of claims 1 to 8, characterized in that: A plurality of measuring point sections are non-uniformly arranged on the main body of the experimental section, and a plurality of temperature measuring points are arranged on each of the measuring point sections; And / or, measuring points for the working fluid are provided at the entrance and exit of the experimental device and the entrance and exit of the experimental section.

10. An experimental method for flow instability of the first wall of a fusion reactor water-cooled blanket, characterized in that: The fusion reactor water-cooled blanket first wall flow instability experimental device according to any one of claims 1 to 9 is used, and the experimental method comprises the following steps: Connect the corresponding pipelines of the experimental device according to the actual working conditions to make them consistent with the actual working conditions; Determine the operating parameters of the experimental device according to the actual working conditions, so that the working fluid in the experimental device flows according to the operating parameters; Monitor the corresponding parameters of the working fluid at the outlet of the experimental section until the corresponding parameters are stable; Continuously increase the power of the heating component in predetermined steps until the corresponding parameters are stable; When the medium flow at the outlet of the experimental section oscillates, the power applied to the heating component is the critical power of flow instability.

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