Experimental apparatus and method for flow instability of the first wall of the water-cooled blanket of a fusion reactor

Abstract

This invention discloses an experimental apparatus and method for investigating the flow instability of the first wall of a fusion reactor's water-cooled blanket. The experimental apparatus includes: an experimental section, an inlet manifold, an outlet manifold, and a connecting pipe assembly; the connecting pipe assembly includes multiple connecting pipes; the experimental section includes a main body, with a first channel and a second channel internally; the inlet manifold includes an inlet manifold body and at least two inlet manifold connectors, which are respectively connected to the first and second channels; the outlet manifold includes an outlet manifold body and at least two outlet manifold connectors, which are respectively connected to the first and second channels; the experimental section body, the inlet manifold, and the outlet manifold are connected by the connecting pipe assembly to form two flow paths. The use of a two-channel slice model preserves the structural characteristics of the first wall of the fusion reactor's water-cooled blanket to the greatest extent, effectively reflecting the flow instability characteristics of the first wall and reducing experimental costs.

Description

Technical Field

[0001] This invention relates to experimental apparatus, specifically to an experimental apparatus and method for experimentally determining the instability of the first wall of the water-cooled blanket in a fusion reactor. Background Technology

[0002] The first wall, as a crucial component directly exposed to high-temperature plasma in a nuclear fusion reactor, must withstand complex thermal stresses caused by high heat flux density, high-pressure working fluid, temperature gradients, and thermal expansion. These harsh conditions require the first wall to not only possess excellent cooling capabilities for rapid heat dissipation and maintenance of material integrity, but also sufficient structural strength to cope with various complex mechanical stresses generated during operation. Therefore, the water-cooled ceramic breeder blanket of the fusion engineering experimental reactor uses square parallel channels as the cooling structure for the first wall. Taking the equatorial plane 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 channels not only leads to overall flow instability, but also causes some instabilities unique to parallel channels due to the interaction between the channels, resulting in continuous oscillations, thereby reducing the operating performance of the equipment and the safety of the system.

[0003] Existing experimental setups for flow instability are mostly derived from studies of steam generators. Therefore, the designed experimental sections typically have the following characteristics: 1. The channels are circular; 2. The circular tube channel serves as a heat source, providing a uniform circumferential heat flow to the experimental section; 3. The experimental channels are independent and do not contact each other, with no heat exchange between them; 4. The working fluid flows in the same direction in both channels. However, these characteristics deviate from the cooling design of the first wall of the water-cooled blanket in fusion reactors. Experimental data obtained through these setups cannot reflect the flow instability characteristics of the first wall of the water-cooled blanket in fusion reactors.

[0004] Therefore, there is a need for an experimental apparatus for the flow instability of the first wall of the water-cooled blanket of a fusion reactor. Summary of the Invention

[0005] To address the aforementioned technical problems, this invention provides an experimental apparatus for the flow instability of the first wall of a fusion reactor water-cooled blanket. This apparatus retains the key features and structure of the first wall of the fusion reactor water-cooled blanket, simplifies experimental costs, and enables the acquisition of practically valuable experimental data at low cost.

[0006] Accordingly, the present invention also provides a method for conducting experiments on the instability of the first wall of a fusion reactor water-cooled blanket using the above-mentioned experimental apparatus for the instability of the first wall of a fusion reactor water-cooled blanket.

[0007] An experimental apparatus for flow instability in the first wall of a water-cooled blanket of a fusion reactor, the apparatus comprising: an experimental section, an inlet header, an outlet header, and a connecting pipe assembly; the experimental section, the inlet header, and the outlet header are connected by the connecting pipe assembly; the connecting pipe assembly comprises multiple connecting pipes.

[0008] The experimental section includes a main body, inside which a first channel and a second channel are provided; the inlet manifold includes an inlet manifold body and at least two inlet manifold connectors; the two inlet manifold connectors 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 connectors, the outlet manifold connectors are respectively connected to the first channel and the second channel; the main body of the experimental section, the inlet manifold, and the outlet manifold are connected by a connecting pipe assembly to form two flow paths.

[0009] The two inlet manifold connectors are located on both sides of the inlet manifold body; the two outlet manifold connectors are located on both sides of the outlet manifold body.

[0010] And / or, the two inlet manifold connectors are located on one side of the inlet manifold body; the two outlet manifold connectors are located on one side of the outlet manifold body.

[0011] The inlet manifold has three connectors: two connectors are located on one side of the inlet manifold body, and the other connector is located on the other side of the inlet manifold body.

[0012] There are three export manifold connectors, with two connectors located on one side of the export manifold body and the other connector located on the other side of the export manifold body.

[0013] The inlet manifold has four connectors, with two connectors located on one side of the inlet manifold body and the other two connectors located on the other side of the inlet manifold body.

[0014] There are four export manifold connectors, with two connectors located on one side of the export manifold body and the other two connectors located on the other side of the export manifold body.

[0015] The experimental apparatus for the flow instability of the first wall of the water-cooled blanket of the fusion reactor also includes a plug for sealing the outlet manifold or the inlet manifold.

[0016] A heating element is provided on the plasma-facing side of the main body of the experimental section.

[0017] Both the first and second channels are square channels.

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

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

[0020] And / or, measurement points for the working fluid are set at both the inlet and outlet of the experimental apparatus and the inlet and outlet of the experimental section.

[0021] An experimental method for detecting flow instability in the first wall of a water-cooled blanket in a fusion reactor, using the aforementioned experimental apparatus, includes the following steps:

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

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

[0024] Monitor the relevant parameters of the working medium at the outlet of the experimental section until the relevant parameters stabilize;

[0025] The power of the heating element is continuously increased in predetermined steps until the corresponding parameters stabilize.

[0026] When the flow rate of the medium at the outlet of the experimental section oscillates, the power applied to the heating element at this time is the critical power for flow instability.

[0027] The beneficial effects of this invention are:

[0028] (1) This invention uses two channel slices as experimental sections, which significantly reduces experimental costs and obtains acceptable experimental data reliability. The two-channel design is used to simulate the prototype of the first wall. The simulation study found that the experimental results of the two channels deviate from the results of the prototype of the first wall by less than 6.5%. The two-channel slice model preserves 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, it simplifies the experimental cost.

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

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

[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, it retains the characteristic of heat exchange between the channels of the first wall of the fusion reactor.

[0032] (5) The experimental device can quickly switch between the two flow channels in the experimental section in the counter-current and co-current states by changing the connecting pipe group, thus expanding the application range of the experimental device. Attached Figure Description

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

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

[0035] Figure 3 This is a process flow diagram of the experimental apparatus for the first wall flow instability of the fusion reactor water-cooled blanket according to the present invention.

[0036] Wherein: 1-Main body of the experimental section; 11-First experimental section connector; 12-Second experimental section connector; 13-Third experimental section connector; 14-Fourth experimental section connector; 2-Inlet manifold body; 20-Inlet manifold inlet; 21-First inlet manifold connector; 22-Second inlet manifold connector; 23-Third inlet manifold connector; 24-Fourth inlet manifold connector; 3-Outlet manifold body; 30-Outlet manifold outlet; 31-First outlet manifold connector; 32-Second outlet manifold connector; 33-Third outlet manifold connector; 34-Fourth outlet manifold connector; 4-Heating component; 5-Connecting pipe assembly; 6-Plug. Detailed Implementation

[0037] To make the objectives, technical solutions, and advantages of this invention clearer, the invention will be further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the invention. Furthermore, the technical features involved in the various embodiments of this invention described below can be combined with each other as long as they do not conflict with each other.

[0038] See Figure 1 This invention provides an experimental apparatus for flow instability of the first wall of a water-cooled blanket in a fusion reactor. The experimental apparatus includes: an experimental section, an inlet header, an outlet header, and a connecting pipe assembly 5; the experimental section, the inlet header, and the outlet header are connected by the connecting pipe assembly; the connecting pipe assembly includes multiple connecting pipes.

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

[0040] The first wall of a fusion reactor's water-cooled blanket typically consists of dozens of square parallel channels. Conducting experiments directly on a prototype would be extremely costly, and current heating technologies cannot provide sufficiently high heat flux for the experimental device. Considering that the first wall channels are multiple repetitions of square channels in the poloidal direction, a representative two-channel slice model was extracted as the experimental segment. This invention uses two channels (the first channel and the second channel) as the experimental segment, significantly reducing experimental costs and achieving acceptable experimental data reliability. Simulation studies using a two-channel design to simulate the first wall prototype showed that the results of the two-channel experimental segment deviated from the results of the first wall prototype by less than 6.5%. The two-channel slice model maximally preserves the structural characteristics of the first wall of the fusion reactor's water-cooled blanket, and the experimental data can well reflect the flow instability characteristics of the first wall; at the same time, it simplifies experimental costs.

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

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

[0043] Furthermore, there are three inlet manifolds: two are located on one side of the inlet manifold body, and the other is located on the other side. Similarly, there are three outlet manifolds: two are located on one side of the outlet manifold body, and the other is located on the other side. The experimental setup in this embodiment can switch between co-current and counter-current states simply by connecting the corresponding inlet and outlet manifolds to either the first or second channel.

[0044] More preferably, in this embodiment, there are four inlet manifold connectors: two are located on one side of the inlet manifold body, and the other two are located on the other side; similarly, there are four outlet manifold connectors: two are located on one side of the outlet manifold body, and the other two are located on the other side. See also... Figure 1 The system comprises four inlet manifold connectors: a first inlet manifold connector 21, a second inlet manifold connector 22, a third inlet manifold connector 23, and a fourth inlet manifold connector 24. The first and second inlet manifold connectors 21 and 22 are located on one side of the inlet manifold body 2, while the third and fourth inlet manifold connectors 23 and 24 are located on the other side. Similarly, the system comprises four outlet manifold connectors: a first outlet manifold connector 31, a second outlet manifold connector 32, a third outlet manifold connector 33, and a fourth outlet manifold connector 34. The first and second outlet manifold connectors 31 and 32 are located on one side of the outlet manifold body 3, while the third and fourth outlet manifold connectors 33 and 34 are located on the other side. By changing the connecting pipe assemblies, the two flow channels in the experimental section can be quickly switched between counter-current and co-current states, expanding the application range of the experimental device.

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

[0046] For an even better option, see [link to previous section]. Figure 1 When there are more than two inlet manifolds or more than two outlet manifolds, plug 6 can be used to seal the temporarily unused outlet manifolds or inlet manifolds. Plug 6 is threadedly connected to both the inlet and outlet manifolds.

[0047] The test section pipe connections, connecting pipe assemblies, inlet manifold connections, and outlet manifold connections are welded using argon arc welding.

[0048] For an even better option, see [link to previous section]. Figure 1A heating element 4 is provided on the plasma-facing side of the outer wall of the experimental section body 1. In this embodiment, the heating element is an electric heating film. Using an electric heating film as the sole heat source and fused to one side of the experimental section provides the experimental section with the same heat flow characteristics as the prototype first wall of a fusion reactor compared to existing flow instability experimental devices. The electric heating film is fused to the surface of the experimental section body 1. The electric heating film is fused to the plasma-facing side of the experimental section and is the only heat source, providing a unidirectional heat flow. The first wall of the fusion reactor water-cooled blanket mainly bears the high-density heat flow from the high-temperature plasma. Due to the structural characteristics of the fusion reactor, the high heat flow only exists on the plasma-facing side of the first wall; therefore, the first wall bears a unilateral high heat flow. The flow instability experimental device for the first wall of the fusion reactor water-cooled blanket of this invention uses an electric heating film as the heat source, fused only to the plasma-facing side of the experimental section, providing the experimental section with heat flow conditions consistent with the prototype first wall.

[0049] Preferably, both the first and second channels are square channels. Using square channels as cooling channels retains the same structural characteristics as the prototype cooling channels of the first wall of a fusion reactor compared to existing flow instability experimental devices. Their dimensions are consistent with the channel structure dimensions of the actual first wall of a fusion reactor.

[0050] Preferably, the first and second channels are fabricated from the same piece of material, and the coolant in the two channels exchanges heat through a shared wall. This design retains the characteristic of heat exchange between the first wall channels of a fusion reactor, compared to existing flow-unstable experimental devices.

[0051] In one embodiment, considering that the temperature distribution of the experimental section channel satisfies centrosymmetry, and in order to obtain more data at the lowest cost, multiple measuring point sections are non-uniformly arranged on the main body 1 of the experimental section, and multiple temperature measuring points are arranged on each measuring point section. See also Figure 2 In this embodiment, starting from the end of the left curved section of the main body 1 of the experimental section, eight measuring point sections, numbered A to H, were non-uniformly set; each measuring point section had 13 temperature measuring points. Among them, one thermocouple was set for each thermocouple with a hole diameter of 0.6mm, two thermocouples with a hole diameter of 1mm and an axial distance of 5mm were set, and three thermocouples with a hole diameter of 1.5mm and an axial distance of 5mm were set.

[0052] Preferably, measurement points for the working fluid are provided at both the inlet and outlet of the experimental apparatus and the inlet and outlet of the experimental section. Measurement points for the working fluid are provided at the inlet and outlet of the experimental apparatus and at the inlet and outlet of the main body 1 of the experimental section. See [link / reference] Figure 1The working fluid pressure, temperature, and flow rate were measured at the inlet manifold inlet 20 and the outlet manifold outlet 30. The working fluid pressure, temperature, and flow rate were also measured at the first test section connector 11 and the third test section connector 13. The pressure difference between the outlet and inlet of each channel in the test section was also measured.

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

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

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

[0056] Monitor the relevant parameters of the working fluid at the outlet of the test section until the relevant parameters stabilize; the relevant parameters include pressure, temperature and flow rate;

[0057] The power of the heating element is continuously increased in predetermined steps until the corresponding parameters stabilize; the predetermined steps are determined according to actual needs.

[0058] When the flow rate of the medium at the outlet of the experimental section oscillates, the power applied to the heating component at this point is the critical power for flow instability. This power can be converted to obtain the flow instability boundary of the first wall of the water-cooled ceramic breeder blanket in the China Fusion Engineering Experimental Reactor.

[0059] For details, see Figure 3 During the experiment, the working fluid within the experimental setup flowed according to the operating parameters. Starting from zero, the power of the electric heating membrane was increased in 1 kW increments. After each power increase, the working fluid pressure, temperature, and flow rate at the outlet of experimental section 1 were monitored. After the working fluid parameters stabilized for one minute, the power of the electric heating membrane was increased again in one increment. These steps were repeated until the flow rate at the outlet of experimental section 1 oscillated. The power applied to experimental section 1 by the electric heating membrane at the point of oscillation was the critical power for flow instability in that experimental section. This power, through calculation, yielded the flow instability boundary of the first wall of the water-cooled ceramic breeder blanket of the China Fusion Engineering Experimental Reactor.

[0060] In the description of this invention, "a plurality of" means at least two, such as two, three, etc., unless otherwise explicitly specified.

[0061] In the description of this specification, the references to "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., indicate that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of the present invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Moreover, without contradiction, those skilled in the art can combine and integrate the different embodiments or examples described in this specification, as well as the features of different embodiments or examples.

[0062] Those skilled in the art will readily understand that the above description is merely 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 within the scope of protection of the present invention.

[0063] The parts of this invention not described in detail are well-known in the art. The above embodiments are provided merely for the purpose of describing the invention and are not intended to limit the scope of the invention. The scope of the invention is defined by the appended claims. All equivalent substitutions and modifications made without departing from the spirit and principles of the invention should be covered within the scope of the invention.

Claims

1. An experimental apparatus for flow instability in the first wall of a water-cooled blanket of a fusion reactor, characterized in that, The experimental apparatus includes: an experimental section, an inlet manifold, an outlet manifold, and a connecting pipe assembly; the experimental section, the inlet manifold, and the outlet manifold are connected by the connecting pipe assembly; the connecting pipe assembly includes multiple connecting pipes; The experimental section includes a main body, inside which a first channel and a second channel are provided; the inlet manifold includes an inlet manifold body and at least two inlet manifold connectors; the two inlet manifold connectors 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 connectors, the outlet manifold connectors are respectively connected to the first channel and the second channel; the main body of the experimental section, the inlet manifold, and the outlet manifold are connected by a connecting pipe assembly to form two flow paths; A heating element is provided on the plasma-facing side of the main body of the experimental section; the first channel and the second channel are processed from the same material, and the two channels achieve heat exchange through a shared wall.

2. The experimental apparatus for flow instability of the first wall of the water-cooled blanket of a fusion reactor according to claim 1, characterized in that, The two inlet manifold connectors are located on both sides of the inlet manifold body; the two outlet manifold connectors are located on both sides of the outlet manifold body. And / or, the two inlet manifold connectors are located on one side of the inlet manifold body; the two outlet manifold connectors are located on one side of the outlet manifold body.

3. The experimental apparatus for flow instability of the first wall of the water-cooled blanket of a fusion reactor according to claim 1, characterized in that, There are three inlet manifolds, two of which are located on one side of the inlet manifold body and the other inlet manifold is located on the other side of the inlet manifold body. There are three export manifold connectors, with two connectors located on one side of the export manifold body and the other connector located on the other side of the export manifold body.

4. The experimental apparatus for flow instability of the first wall of the water-cooled blanket of a fusion reactor according to claim 1, characterized in that, There are four inlet manifolds, with two inlet manifolds located on one side of the inlet manifold body and the other two inlet manifolds located on the other side of the inlet manifold body. There are four export manifold connectors, with two connectors located on one side of the export manifold body and the other two connectors located on the other side of the export manifold body.

5. The experimental apparatus for flow instability of the first wall of the water-cooled blanket of a fusion reactor according to claim 4, characterized in that, The experimental apparatus for the first wall flow instability of the fusion reactor water-cooled blanket also includes a plug for sealing the outlet manifold or the inlet manifold.

6. The experimental apparatus for flow instability of the first wall of the water-cooled blanket of a fusion reactor according to claim 1, characterized in that, Both the first and second channels are square channels.

7. The experimental apparatus for flow instability of the first wall of the water-cooled blanket of a fusion reactor according to any one of claims 1 to 6, characterized in that, Multiple measuring point sections are non-uniformly arranged on the main body of the experimental section, and multiple temperature measuring points are arranged on each measuring point section; And / or, measurement points for the working fluid are set at both the inlet and outlet of the experimental apparatus and the inlet and outlet of the experimental section.

8. An experimental method for detecting flow instability in the first wall of a water-cooled blanket in a fusion reactor, characterized in that, The experimental apparatus for experimental instability of the first wall of the water-cooled blanket of a fusion reactor, as described in any one of claims 1 to 7, comprises the following steps: Connect the corresponding pipelines of the experimental device according to the actual operating conditions to make them consistent with the actual operating conditions; Determine the operating parameters of the experimental device based on the actual working conditions, so that the working fluid in the experimental device flows according to the operating parameters; Monitor the relevant parameters of the working medium at the outlet of the experimental section until the relevant parameters stabilize; The power of the heating element is continuously increased in predetermined steps until the corresponding parameters stabilize. When the flow rate of the medium at the outlet of the experimental section oscillates, the power applied to the heating element at this time is the critical power for flow instability.

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