In-situ surface treatment method of tungsten first wall, tungsten first wall and fusion device

Abstract

The application discloses a surface in-situ processing method of a tungsten first wall of a fusion device, comprising: heating the tungsten first wall to a preset temperature interval, wherein the preset temperature interval is [700 DEG C, 1300 DEG C]. Based on a preset irradiation mode, pre-injected helium gas is processed to generate a helium plasma and control incident ion energy of the helium plasma reaching the tungsten first wall to be in a preset energy interval, wherein the preset energy interval is [20 eV, 100 eV]. According to the helium plasma, the tungsten first wall in the preset temperature interval is irradiated and processed until a cumulative helium ion fluence of the tungsten first wall meets a preset condition, so as to in-situ generate a tungsten villus layer and a helium bubble on the tungsten first wall, wherein the preset condition is that the cumulative helium ion fluence is greater than 1.0 x 10 22 He / m 2. In this way, the tungsten villus layer can reduce the net sputtering yield of tungsten and avoid contamination of the helium plasma by tungsten ions. The helium bubble can inhibit recrystallization nucleation and grain growth at high temperature.

Description

Technical Field

[0001] This invention relates to the field of nuclear fusion technology, and in particular to a method for in-situ surface treatment of the tungsten first wall of a fusion device, the tungsten first wall, and the fusion device. Background Technology

[0002] In related technologies, tungsten first walls, made of tungsten materials, are commonly used in nuclear fusion devices due to their high melting point, low sputtering rate, and low tritium retention. As components directly exposed to plasma, they withstand plasma bombardment. However, during service, the surface of the tungsten first wall is prone to recrystallization embrittlement, grain coarsening, physical sputtering, and hydrogen isotope infiltration, making it difficult for tungsten first walls to meet the requirements of nuclear fusion devices. Summary of the Invention

[0003] This application provides a method for in-situ surface treatment of the tungsten first wall of a fusion device, the tungsten first wall, and the fusion device.

[0004] This application provides an in-situ surface treatment method for the first tungsten wall of a fusion device, the method comprising:

[0005] The tungsten first wall is heated to a preset temperature range, which is [700℃, 1300℃];

[0006] Based on a preset irradiation mode, the pre-injected helium gas is processed to generate helium plasma and the energy of the incident ions reaching the first tungsten wall of the helium plasma is controlled to be within a preset energy range, which is [20eV, 100eV].

[0007] According to the helium plasma, the tungsten first wall within the preset temperature range is irradiated until the cumulative helium ion flux of the tungsten first wall meets a preset condition, so as to generate a tungsten wool layer and helium bubbles in situ on the tungsten first wall. The preset condition is that the cumulative helium ion flux is greater than .

[0008] Thus, the first tungsten wall is heated to a preset temperature range, which is [700℃, 1300℃]. Next, based on a preset irradiation mode, the pre-injected helium gas is processed to generate helium plasma, and the incident ion energy of the helium plasma reaching the first tungsten wall is controlled within a preset energy range, which is [20eV, 100eV]. Subsequently, the first tungsten wall within the preset temperature range is irradiated according to the helium plasma until the cumulative helium ion flux of the first tungsten wall meets a preset condition to generate a tungsten wool layer and helium bubbles in situ on the first tungsten wall. The preset condition is that the cumulative helium ion flux is greater than […]. In this way, the generated tungsten wool layer can capture impurity ions that bombard sputtered tungsten atoms, reducing the net sputtering yield of tungsten through a geometric redeposition effect and preventing helium plasma from being contaminated by tungsten ions. The generated helium bubbles can fix the subgrain boundaries or grain boundaries of tungsten through the Zener pinning effect, effectively inhibiting recrystallization nucleation and grain growth at high temperatures and maintaining the mechanical strength of tungsten materials. Furthermore, the tungsten wool layer and the helium bubble network together constitute a diffusion barrier for hydrogen isotopes, which can disrupt the continuous diffusion channels of hydrogen isotopes, reduce the steady-state permeation of hydrogen, deuterium, and tritium ions in the tungsten matrix, and ensure the safety of the fusion device. In addition, the tungsten wool layer also has low Young's modulus and foam-like properties, allowing it to expand and contract freely, releasing surface thermal stress under transient thermal loads and improving thermal shock resistance.

[0009] In some embodiments, the preset irradiation mode includes a DC glow discharge mode, an ion cyclone treatment mode, and an induced electric field assisted mode.

[0010] Thus, the preset irradiation modes include DC glow discharge mode, ion cyclone wall treatment mode, and induced electric field assisted mode. In this way, by providing irradiation modes such as DC glow discharge mode, ion cyclone wall treatment mode, and induced electric field assisted mode, it is possible to cover all operating conditions of the fusion device from major shutdown and overhaul to daily operation.

[0011] In some embodiments, the step of processing pre-injected helium gas based on a preset irradiation mode to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range includes:

[0012] When the preset irradiation mode is the DC glow discharge mode, the helium pressure in the vacuum chamber where the tungsten first wall is located is controlled to be within the first preset pressure range.

[0013] When the helium gas pressure is within the first preset pressure range, the helium gas is processed according to the preset DC voltage applied to the first tungsten wall to generate the helium plasma and control the incident ion energy to be within the preset energy range, wherein the first tungsten wall is a cathode.

[0014] Thus, with the preset irradiation mode set to DC glow discharge, the helium pressure in the vacuum chamber containing the tungsten first wall is controlled within a first preset pressure range. Next, while the helium pressure is within this range, the helium is processed according to a preset DC voltage applied to the tungsten first wall to generate helium plasma, and the incident ion energy is controlled within a preset energy range, with the tungsten first wall serving as the cathode. In this way, under DC glow discharge mode, by controlling factors such as the helium pressure in the vacuum chamber and the preset DC voltage, a tungsten wool layer and helium bubbles can be stably generated in situ on the tungsten first wall.

[0015] In some embodiments, the step of processing pre-injected helium gas based on a preset irradiation mode to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range includes:

[0016] When the preset irradiation mode is the ion cyclone wall treatment mode, under a magnetic field environment with a preset magnetic field strength, the helium pressure in the vacuum chamber where the tungsten first wall is located is controlled to be within the second preset pressure range.

[0017] When the helium gas pressure is within the second preset pressure range, the helium gas is processed according to the radio frequency wave emitted by the ion cyclotron resonance heating antenna of the fusion device to generate the helium plasma and control the incident ion energy to be within the preset energy range.

[0018] Thus, under the preset irradiation mode of ion cyclotron wall treatment, and in a magnetic field environment with a preset magnetic field strength, the helium pressure in the vacuum chamber where the first tungsten wall is located is controlled within a second preset pressure range. Then, with the helium pressure within the second preset pressure range, the helium is processed according to the radio frequency wave emitted by the ion cyclotron resonant heating antenna of the fusion device to generate helium plasma, and the incident ion energy is controlled within a preset energy range. In this way, under the ion cyclotron wall treatment mode, by controlling the helium pressure in the vacuum chamber and related factors such as the radio frequency wave, a tungsten wool layer and helium bubbles can be stably generated in situ on the first tungsten wall.

[0019] In some embodiments, the frequency of the radio frequency wave is matched with the cyclotron resonance frequency of helium ions in the magnetic field environment, and the power of the radio frequency wave is within a preset power range.

[0020] In this way, the frequency of the radio frequency wave matches the cyclotron resonance frequency of helium ions in a magnetic field environment, and the power of the radio frequency wave is within a preset power range. Thus, by controlling the radio frequency wave frequency to match the cyclotron resonance frequency and controlling the power of the radio frequency wave within a preset power range, the repair and growth of the tungsten wool layer can be completed quickly.

[0021] In some embodiments, the step of processing pre-injected helium gas based on a preset irradiation mode to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range includes:

[0022] When the preset irradiation mode is the induced electric field assisted mode, the helium pressure in the vacuum chamber where the tungsten first wall is located is controlled to be in the third preset pressure range.

[0023] When the helium gas pressure is within the third preset pressure range, the central solenoid coil of the fusion device is excited to generate an induced electric field.

[0024] Based on the induced electric field, the helium gas is broken down to generate an initial helium plasma;

[0025] The initial helium plasma is processed according to a preset auxiliary heating method to generate the helium plasma and control the energy of the incident ions to be within the preset energy range.

[0026] Thus, with the preset irradiation mode set to induced electric field assisted mode, the helium pressure in the vacuum chamber containing the first tungsten wall is controlled within a third preset pressure range. Next, with the helium pressure within this range, the central solenoid coil of the fusion device is excited, generating an induced electric field. Subsequently, based on this field, the helium gas is broken down, generating initial helium plasma. Finally, according to a preset auxiliary heating method, the initial helium plasma is processed to generate more helium plasma, and the incident ion energy is controlled within a preset energy range. In this way, under the ion cyclone wall processing mode, by controlling factors such as the helium pressure in the vacuum chamber, the induced electric field, and the preset auxiliary heating method, a stable in-situ generation of a tungsten wool layer and helium bubbles can be achieved on the first tungsten wall.

[0027] In some embodiments, the preset auxiliary heating method includes at least one of electron cyclotron resonance heating, ion cyclotron resonance heating, and neutral beam injection.

[0028] Thus, the preset auxiliary heating methods include at least one of electron cyclotron resonance heating, ion cyclotron resonance heating, and neutral beam injection. This allows for the selection of one heating method to be used alone, or a combination of two or more, depending on the fusion device's equipment configuration, to adapt to different device hardware conditions and ensure heating efficiency and energy control precision.

[0029] In some embodiments, the tungsten fluff layer is a mesh structure formed by interwoven nanofibers, and the thickness of the tungsten fluff layer is [0.1μm, 10μm].

[0030] Thus, the tungsten fluff layer is a mesh structure formed by interwoven nanofibers, with a thickness of [0.1 μm, 10 μm]. The high specific surface area and porosity of this nanofiber mesh structure significantly improve the redeposition rate of tungsten atoms sputtered by impurity ions, effectively reducing net sputtering yield.

[0031] In some embodiments, the helium bubble is located in the subsurface layer of the first tungsten wall beneath the tungsten velvet layer.

[0032] Thus, the helium bubbles are located in the subsurface layer of the first tungsten wall beneath the tungsten textural layer. The grain boundary pinning effect of the helium bubbles in this subsurface layer can suppress high-temperature recrystallization and grain growth. Combined with the thermal stress release function of the network structure of the tungsten textural layer, this ensures the crack formation rate of the first tungsten wall under thermal shock.

[0033] This application also provides a tungsten first wall, which is constructed based on the above method.

[0034] This application also provides a fusion device, which includes the aforementioned tungsten first wall.

[0035] Thus, the fusion device provided in this application includes a tungsten first wall, which comprises an in-situ generated tungsten wool layer and helium bubbles. The generated tungsten wool layer can capture impurity ions that bombard sputtered tungsten atoms, reducing the net sputtering yield of tungsten through a geometric redeposition effect and preventing helium plasma from being contaminated by tungsten ions. The generated helium bubbles can fix the subgrain boundaries or grain boundaries of tungsten through the Zener pinning effect, effectively suppressing recrystallization nucleation and grain growth at high temperatures, and maintaining the mechanical strength of the tungsten material. Furthermore, the tungsten wool layer and the helium bubble network together constitute a diffusion barrier for hydrogen isotopes, which can disrupt the continuous diffusion channels of hydrogen isotopes, reduce the steady-state permeation of hydrogen, deuterium, and tritium ions in the tungsten matrix, and ensure the safety of the fusion device. In addition, the tungsten wool layer also has low Young's modulus and foam-like properties, allowing it to expand and contract freely, releasing surface thermal stress under transient thermal loads and improving thermal shock resistance.

[0036] Additional aspects and advantages of embodiments of this application will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of embodiments of this application. Attached Figure Description

[0037] The above and additional aspects and advantages of this application will become apparent and readily understood from the description of the embodiments taken in conjunction with the following drawings, in which:

[0038] Figure 1 This is one of the schematic flowcharts of the surface in-situ treatment method according to certain embodiments of this application;

[0039] Figure 2 This is a second schematic flowchart of a surface in-situ treatment method according to certain embodiments of this application;

[0040] Figure 3 This is the third flowchart of a surface in-situ treatment method according to certain embodiments of this application;

[0041] Figure 4 This is the fourth flowchart of a surface in-situ treatment method according to certain embodiments of this application. Detailed Implementation

[0042] The embodiments of this application are described in detail below. Examples of the embodiments are shown in the accompanying drawings, wherein the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain the embodiments of this application, and should not be construed as limiting the embodiments of this application.

[0043] In related technologies, nuclear fusion devices, as the core equipment for achieving controlled nuclear fusion energy, must withstand extremely harsh plasma environments during operation. This necessitates that components directly exposed to the plasma possess excellent performance. The tungsten first wall, made of tungsten material, is chosen for its high melting point, low sputtering rate, and low tritium retention capacity, making it the component in the nuclear fusion device that directly bears the plasma bombardment. It plays a crucial role in dissipating the heat load of the device, isolating impurity particles, and protecting the device's main structure.

[0044] However, during long-term service, the extreme plasma interaction environment inevitably exposes the tungsten first wall to the risk of failure, making it difficult to meet the long-term, stable operation requirements of nuclear fusion devices. On the one hand, the tungsten first wall needs to continuously withstand the steady-state high-temperature heat load from the plasma, as well as transient thermal shocks such as edge localized modes. Under long-term high-temperature action, the microstructure of tungsten undergoes a recrystallization transformation, and the originally fine and uniform grains gradually coarsen, leading to an increase in the ductile-brittle transition temperature and a decrease in fracture toughness. This causes the tungsten first wall to transform from a ductile material into a brittle material, making it extremely susceptible to microcracks or even spalling during subsequent thermal shocks or mechanical vibrations. On the other hand, although tungsten has a high sputtering threshold, nuclear fusion devices need to inject high atomic number impurity gases such as neon and argon into the vacuum chamber to dissipate the heat load from the first radiative wall. These impurity ions, accelerated in the plasma, bombard the surface of the tungsten first wall at high energy levels, triggering physical sputtering. This causes tungsten atoms to be ejected and enter the plasma region, resulting in permanent damage to the tungsten first wall surface and diluting the concentration of fusion fuel, reducing plasma purity and fusion reaction gain. Furthermore, under continuous bombardment by high-flux hydrogen isotope plasma, despite the low hydrogen solubility of tungsten, a large number of hydrogen isotope atoms can still penetrate into the tungsten first wall matrix through surface adsorption and lattice diffusion. Some may even penetrate the tungsten first wall and enter the device's cooling circuit, potentially reacting with the cooling medium and corroding the circuit pipes. Moreover, the infiltration of radioactive tritium may also pose a risk of radioactive leakage, threatening the operational safety of the device and the health of personnel.

[0045] This results in the service life of the tungsten first wall being far shorter than the design cycle of the nuclear fusion device, making it difficult to meet the usage requirements of the nuclear fusion device.

[0046] Based on the above issues, please refer to Figure 1This application provides an in-situ surface treatment method for the first tungsten wall of a fusion device, the method comprising:

[0047] 01: Heat the first tungsten wall to the preset temperature range;

[0048] 02: Based on the preset irradiation mode, the pre-injected helium gas is processed to generate helium plasma and the energy of the incident ions reaching the first wall of the tungsten is controlled within the preset energy range.

[0049] 03: Based on helium plasma, the first tungsten wall within the preset temperature range is irradiated until the cumulative helium ion flux of the first tungsten wall meets the preset conditions, so as to generate a tungsten wool layer and helium bubbles in situ on the first tungsten wall.

[0050] Specifically, a fusion device refers to a device that uses methods such as magnetic confinement or inertial confinement to induce fusion reactions in light nuclei, such as hydrogen isotopes, under extremely high temperatures and pressures to release energy. In some embodiments, the fusion device may be a tokamak device.

[0051] The first tungsten wall refers to the surface structure in a fusion device that is in direct contact with the plasma. It is the area that is subjected to plasma bombardment, heat load, and erosion by impurities.

[0052] The preset temperature range [700℃, 1300℃] refers to the temperature range of the first wall surface of tungsten that ensures helium plasma irradiation can induce the formation of tungsten velvet layer, which is a necessary condition for the formation of tungsten velvet layer and helium bubble.

[0053] 700℃ is the critical temperature threshold for inducing the formation of tungsten fiber structures. If the temperature of the first tungsten wall is below 700℃, the thermal activation energy of tungsten atoms is insufficient, resulting in extremely weak migration ability. Helium ion bombardment can only cause helium atoms to aggregate in the interstitial spaces of the tungsten lattice to form helium bubble protrusions, but it cannot drive the tungsten atoms to recombine and form a nanofiber network structure. Simultaneously, when the temperature of the first tungsten wall is below 700℃, the helium ion implantation depth is limited, making it difficult to form high-density helium bubbles in the subsurface layer and achieving the grain boundary pinning effect. Setting the lower limit of the preset temperature range to 700℃ provides sufficient migration momentum for tungsten atoms, allowing them to recombine and grow in a specific direction under the bombardment of helium ions, forming a porous and loose villous layer, while ensuring effective helium ion implantation into the subsurface layer to form helium bubbles. 1300℃ is the critical temperature threshold for avoiding excessive recrystallization of the tungsten matrix. If the temperature of the first tungsten wall is above 1300℃, the tungsten matrix itself will undergo significant recrystallization, leading to grain coarsening, decreased mechanical strength, and a high susceptibility to cracking under thermal shock. Meanwhile, when the temperature of the first tungsten wall exceeds 1300℃, the stability of the generated tungsten wool layer structure decreases, potentially leading to fiber melting, structural collapse, or weakened bonding with the matrix. This can cause the wool to easily peel off and form dust during service, thus exacerbating the operational risks of the device. Setting the upper limit of the preset temperature range to 1300℃ provides sufficient power for structure formation while strictly limiting the recrystallization of the tungsten matrix, maintaining the original mechanical strength and toughness of the matrix.

[0054] Helium plasma refers to the plasma state containing helium ions, electrons, and other particles formed after helium gas is ionized.

[0055] Incident ion energy refers to the kinetic energy of helium ions in the helium plasma when they reach the surface of the first tungsten wall. It is a parameter that determines the interaction effect between the ions and the tungsten matrix. When the kinetic energy of helium ions in the helium plasma reaches the surface of the first tungsten wall is within a preset ion energy range, effective injection of the helium plasma can be ensured, and damage to the tungsten matrix can be avoided. It should be noted that, in the embodiments of this application, the preset ion energy range is [20eV, 100eV], which is the optimal range verified by experiments. If the incident ion energy is lower than 20eV, the helium plasma cannot break through the lattice bond of the tungsten surface and cannot induce tungsten atom migration and helium bubble formation. If the incident ion energy is higher than 100eV, the helium plasma will erode the surface of the helium plasma, destroy the integrity of the tungsten matrix, and even cause the generated tungsten fiber structure and helium bubble to peel off.

[0056] The cumulative helium ion fluence refers to the total number of helium ions received per unit area of ​​the tungsten first wall surface during irradiation, and is an indicator of irradiation dose. It should be noted that a sufficient helium ion fluence is a necessary condition to ensure the complete formation of the tungsten velvet layer and helium bubbles. In the in-situ surface treatment method for the tungsten first wall provided in this application, the cumulative helium ion fluence of the tungsten first wall needs to be greater than [amount missing]. When the accumulated helium ion flux is insufficient, tungsten atom migration and recombination are inadequate, failing to form a tungsten wool layer of sufficient thickness and structure. Furthermore, the subsurface helium bubble density is insufficient to achieve functions such as grain boundary pinning. After the value is applied, a tungsten texturized layer with a thickness of 0.1μm-10μm and a high-density subsurface helium bubble can be formed, ensuring that the tungsten first wall has the expected service performance.

[0057] The tungsten velvet layer refers to the nanoscale fibrous network structure generated in situ on the surface of the tungsten first wall through helium plasma irradiation. Characterized by its porous and loose structure, it is the core structure for achieving functions such as sputter resistance and stress relief. Specifically, the tungsten velvet layer can utilize its huge specific surface area and complex pores to capture sputtered atoms through a geometric redeposition effect, significantly reducing impurity contamination. Simultaneously, the foam-like flexible structure of the tungsten velvet layer can buffer and release stress generated by transient high thermal loads, preventing cracking. Furthermore, the tungsten velvet layer, together with the underlying helium bubble network, forms a physical barrier for hydrogen isotope diffusion, reducing tritium permeation, while the pinning effect of the helium bubbles on grain boundaries effectively inhibits high-temperature recrystallization and embrittlement of the tungsten matrix. Most importantly, the tungsten velvet layer can be regenerated in situ through helium plasma irradiation, achieving recyclable maintenance of the surface properties of the tungsten first wall, thereby systematically extending the service life of the tungsten first wall in fusion devices.

[0058] Helium bubbles refer to high-density nanoscale bubbles formed when helium ions are injected into the subsurface layer of a tungsten matrix, where helium is insoluble in tungsten and aggregates to inhibit recrystallization and cracking by pinning grain boundaries. Specifically, helium bubbles effectively pin the grain boundaries and subgrain boundaries of the tungsten first wall, inhibiting recrystallization and grain growth of tungsten materials at high temperatures, thereby maintaining the toughness of the tungsten matrix and preventing embrittlement and cracking. Furthermore, the helium bubble network, together with the tungsten velvet layer on the surface of the tungsten first wall, forms a tortuous barrier against the diffusion of hydrogen isotopes into the deeper layers of the material, significantly reducing the risk of tritium and other ion penetration.

[0059] First, based on the service stage and actual needs of the fusion device, the pretreatment of the tungsten first wall is completed in the vacuum chamber of the fusion device. That is, the temperature of the tungsten first wall is slowly raised to any temperature value between 700℃ and 1300℃, such as 700℃, 800℃ and 900℃, through the baking system or heat sink fluid heating system of the fusion device, and maintained stably to ensure that the thermodynamic conditions meet the standards.

[0060] Next, the energy input system corresponding to the preset irradiation mode is activated to ionize the pre-injected high-purity helium gas into helium plasma. By adjusting the corresponding voltage, power, magnetic field strength and other parameters, the incident energy of helium ions is precisely controlled between 20eV and 100eV, such as 20eV, 35eV, 47eV, 81eV and 100eV.

[0061] Subsequently, the first wall of the tungsten was continuously irradiated, and the cumulative helium ion flux was collected during the process until the cumulative helium ion flux reached a value greater than [value missing]. The preset conditions are met. At this point, a complete tungsten wool layer and subsurface helium bubbles have been formed in situ on the surface of the first tungsten wall. Finally, irradiation is stopped, and the fusion device is restored to normal operation. If the tungsten wool layer is damaged by erosion during subsequent service, the above process can be repeated for in-situ repair.

[0062] In summary, the first tungsten wall is heated to a preset temperature range, which is [700℃, 1300℃]. Next, based on a preset irradiation mode, the pre-injected helium gas is processed to generate helium plasma, and the incident ion energy of the helium plasma reaching the first tungsten wall is controlled within a preset energy range, which is [20eV, 100eV]. Subsequently, the first tungsten wall within the preset temperature range is irradiated according to the helium plasma until the cumulative helium ion flux of the first tungsten wall meets a preset condition to generate a tungsten wool layer and helium bubbles in situ on the first tungsten wall. The preset condition is that the cumulative helium ion flux is greater than […]. In this way, the generated tungsten wool layer can capture impurity ions that bombard sputtered tungsten atoms, reducing the net sputtering yield of tungsten through a geometric redeposition effect and preventing helium plasma from being contaminated by tungsten ions. The generated helium bubbles can fix the subgrain boundaries or grain boundaries of tungsten through the Zener pinning effect, effectively inhibiting recrystallization nucleation and grain growth at high temperatures and maintaining the mechanical strength of tungsten materials. Furthermore, the tungsten wool layer and the helium bubble network together constitute a diffusion barrier for hydrogen isotopes, which can disrupt the continuous diffusion channels of hydrogen isotopes, reduce the steady-state permeation of hydrogen, deuterium, and tritium ions in the tungsten matrix, and ensure the safety of the fusion device. In addition, the tungsten wool layer also has low Young's modulus and foam-like properties, allowing it to expand and contract freely, releasing surface thermal stress under transient thermal loads and improving thermal shock resistance.

[0063] In some implementations, the preset irradiation modes include DC glow discharge mode, ion cyclone treatment mode, and induced electric field assisted mode.

[0064] Specifically, the preset irradiation modes include Direct Current Glow Discharge (GDC), Ion Cyclotron Wall Conditioning (ICWC), and Induced Electric Field Assisted Mode.

[0065] DC glow discharge mode refers to the generation of plasma by ionizing helium gas by applying a DC voltage. By applying a DC voltage between the cathode and anode, the electric field accelerates electrons to collide with helium molecules, causing the helium molecules to ionize and form helium plasma. It has the characteristics of wide processing range and good uniformity, and is suitable for long-term operation.

[0066] The ion cyclone wall treatment mode refers to an irradiation method in which helium gas is ionized and heated by radio frequency waves in a strong magnetic field environment, thereby bombarding the first wall of tungsten. It is suitable for scenarios where a strong magnetic field exists and the processing time is limited.

[0067] The induced electric field-assisted mode refers to the irradiation mode in which an induced electric field is excited by the central solenoid coil of the fusion device, which breaks down helium gas to form initial plasma. This is combined with an auxiliary heating method to enhance the plasma energy. It can utilize the device's existing solenoid system and be adapted to special magnetic field or equipment configuration scenarios.

[0068] Thus, the preset irradiation modes include DC glow discharge mode, ion cyclone wall treatment mode, and induced electric field assisted mode. In this way, by providing irradiation modes such as DC glow discharge mode, ion cyclone wall treatment mode, and induced electric field assisted mode, it is possible to cover all operating conditions of the fusion device from major shutdown and overhaul to daily operation.

[0069] Please see Figure 2 In some embodiments, step 02 (based on a preset irradiation mode, processing the pre-injected helium gas to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range) includes:

[0070] 021: When the preset irradiation mode is DC glow discharge mode, control the helium pressure in the vacuum chamber where the first tungsten wall is located to be within the first preset pressure range.

[0071] 022: When the helium gas pressure is within the first preset pressure range, the helium gas is processed according to the preset DC voltage applied to the first wall of the tungsten gas to generate helium plasma and control the incident ion energy to be within the preset energy range.

[0072] Specifically, the first preset pressure range refers to the helium pressure range adapted to the DC glow discharge mode. This range balances plasma stability with the probability of ion collisions and scattering, ensuring that helium can be broken down by a DC voltage to form a stable glow discharge, while also allowing for appropriate ion energy distribution regulation through moderate collisions between ions. The first preset pressure range can be determined according to actual needs. In some embodiments, the first preset pressure range is typically 0.1 Pa to 10 Pa. When the preset irradiation mode is DC glow discharge, the helium pressure in the vacuum chamber can be any pressure between 0.1 Pa and 10 Pa.

[0073] It should be noted that in the DC glow discharge mode, the first tungsten wall needs to be set as the cathode so that the strong electric field generated by the cathode sheath, i.e. the potential abrupt change region between the cathode surface and the helium plasma, can provide a power source for the directional acceleration of helium ions.

[0074] The preset DC voltage refers to the DC voltage adapted to the first preset gas pressure range. Its value directly determines the potential drop intensity of the cathode sheath, thus affecting the acceleration effect and final energy of helium ions. In some embodiments, the preset DC voltage can typically be any voltage within the range of 150V-500V. The value of the preset DC voltage can be determined according to actual needs.

[0075] First, the vacuum chamber of the fusion device is evacuated to... Below Pa, impurities such as air and water vapor are eliminated to ensure the purity of the helium plasma. Subsequently, the temperature of the first tungsten wall is slowly raised to 700℃-1300℃ and maintained stably using the device's built-in baking system or heat sink fluid heating system to meet the thermodynamic conditions for the formation of the fluff layer. High-purity helium is then injected into the vacuum chamber, and the gas flow controller adjusts the inlet and vacuum pumping rates to stabilize the helium pressure in the vacuum chamber within the first preset range.

[0076] Next, the first wall of the tungsten is grounded via a wire or connected to a negative high voltage, and a DC power supply is started, applying a preset DC voltage. The glow discharge phenomenon is observed to ensure the formation of a stable and uniform glow, avoiding unstable states such as arc discharge. In this way, after the DC voltage breaks down the helium gas, a uniform plasma including helium ions and electrons can be formed. Furthermore, the potential drop of the cathode sheath will directionally accelerate the helium ions, keeping the average incident energy of the helium ions within a preset energy range.

[0077] In some implementations, the irradiation process is also monitored and data is fed back. For example, the DC voltage is continuously monitored to ensure voltage stability. The intensity of tungsten atomic spectral lines is monitored using a spectrometer to determine if there is excessive sputtering; if the spectral line intensity is too high, the voltage is appropriately reduced or the gas pressure is adjusted. Furthermore, changes in the emissivity of the tungsten first wall surface are monitored using an infrared thermometer to indirectly determine the progress of the villous layer growth.

[0078] Thus, with the preset irradiation mode set to DC glow discharge, the helium pressure in the vacuum chamber containing the tungsten first wall is controlled within a first preset pressure range. Next, while the helium pressure is within this range, the helium is processed according to a preset DC voltage applied to the tungsten first wall to generate helium plasma, and the incident ion energy is controlled within a preset energy range, with the tungsten first wall serving as the cathode. In this way, under DC glow discharge mode, by controlling factors such as the helium pressure in the vacuum chamber and the preset DC voltage, a tungsten wool layer and helium bubbles can be stably generated in situ on the tungsten first wall.

[0079] Please see Figure 3 In some embodiments, step 02 (based on a preset irradiation mode, processing the pre-injected helium gas to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range) includes:

[0080] 023: When the preset irradiation mode is the ion cyclone wall treatment mode, under the magnetic field environment of the preset magnetic field strength, the helium gas pressure in the vacuum chamber where the first tungsten wall is located is controlled to be within the second preset pressure range.

[0081] 024: When the helium gas pressure is within the second preset pressure range, the helium gas is processed according to the radio frequency wave emitted by the ion cyclotron resonance heating antenna of the fusion device to generate helium plasma and control the incident ion energy to be within the preset energy range.

[0082] Specifically, for applications requiring strong magnetic fields and short time windows, an ion cyclone wall treatment mode can be used to generate helium plasma that meets the requirements.

[0083] The preset magnetic field strength refers to the range of magnetic field strength adapted to the ion cyclone wall treatment mode. This preset magnetic field strength enables helium ions to generate stable cyclone motion, providing a basis for radio frequency resonant heating. Precise control of the magnetic field strength directly affects the ion cyclone frequency and resonance effect. In some embodiments, the preset magnetic field strength can be 1.5T-4T.

[0084] The second preset pressure range refers to the helium pressure range suitable for strong magnetic fields and radio frequency resonant ionization. This second preset pressure range ensures that the helium molecule density meets the requirements for efficient ionization while reducing helium ion collision losses, ensuring that helium ions obtain sufficient energy and maintain their directional motion. The second preset pressure range can be determined according to actual needs. In some embodiments, the second preset pressure range can be 0.01 Pa to 2 Pa.

[0085] An ion cyclotron resonance heating antenna is a component in a fusion device used to emit radio frequency waves of a specific frequency. The radio frequency wave emitted by the ion cyclotron resonance heating antenna can precisely match the cyclotron resonance frequency of helium ions in a preset magnetic field, making it a key device for achieving efficient heating and acceleration of ions.

[0086] Radio frequency (RF) waves refer to the energy carriers that are heated by ion cyclotron resonance. When the frequency of the RF wave matches the cyclotron frequency of helium ions, the helium ions will continuously absorb the energy of the RF wave, achieving ionization and kinetic energy enhancement. The power and frequency of the RF wave directly determine the plasma density and ion energy.

[0087] Cyclone resonance frequency refers to the natural frequency of helium ions moving in uniform circular motion in a preset magnetic field. When the frequency of radio frequency waves matches this frequency, the ions are in a resonant state and can efficiently absorb radio frequency energy. It is a parameter for achieving rapid acceleration of ions and precise energy control.

[0088] First, the superconducting longitudinal field coil is kept energized to place the fusion device in a magnetic field environment with a preset magnetic field strength. Then, high-purity helium is injected into the vacuum chamber, and the helium pressure in the vacuum chamber is stabilized within a second preset range through coordinated regulation by a high-precision gas flow controller and the vacuum pumping system.

[0089] Subsequently, the cyclotron resonance frequency of the helium ions was calculated based on the current magnetic field strength, and the radio frequency of the ion cyclotron resonance heating antenna was adjusted to this value to ensure precise frequency matching. The power and output mode of the radio frequency wave were then set.

[0090] Next, the ion cyclotron resonance heating antenna is activated to emit radio frequency waves. These waves resonate with helium ions in a strong magnetic field, causing the helium ions to continuously absorb energy and ionize, forming a high-density plasma. During the resonance heating process, the kinetic energy of the helium ions continuously increases. Under the confinement of the magnetic field and the control of the gas pressure, the energy of the ions that eventually strike the surface of the first tungsten wall stabilizes within a preset range of 20 eV-100 eV.

[0091] In some implementations, the irradiation process is also monitored and data is fed back. For example, plasma density is monitored in real time using a plasma density detector to ensure that the irradiation flux meets the standard. The intensity of tungsten atomic spectral lines is monitored using a spectrometer to determine if there is excessive sputtering, and if the intensity is abnormal, the radio frequency power or gas pressure is adjusted. Infrared thermometers are used to monitor the temperature of the first tungsten wall to ensure that it remains within a preset range until the villous layer repair or growth is completed.

[0092] Thus, under the preset irradiation mode of ion cyclotron wall treatment, and in a magnetic field environment with a preset magnetic field strength, the helium pressure in the vacuum chamber where the first tungsten wall is located is controlled within a second preset pressure range. Then, with the helium pressure within the second preset pressure range, the helium is processed according to the radio frequency wave emitted by the ion cyclotron resonant heating antenna of the fusion device to generate helium plasma, and the incident ion energy is controlled within a preset energy range. In this way, under the ion cyclotron wall treatment mode, by controlling the helium pressure in the vacuum chamber and related factors such as the radio frequency wave, a tungsten wool layer and helium bubbles can be stably generated in situ on the first tungsten wall.

[0093] In some implementations, the frequency of the radio frequency wave is matched with the cyclotron resonance frequency of helium ions in a magnetic field environment, and the power of the radio frequency wave is within a preset power range.

[0094] Specifically, the frequency of the radio frequency wave must be precisely matched with the cyclotron resonance frequency of helium ions under the current magnetic field strength. When the frequency of the radio frequency wave does not match the cyclotron frequency of the helium ions, the helium ions cannot effectively absorb radio frequency energy and can only form low-energy plasma through collisional ionization, which cannot meet the ion energy requirements.

[0095] The preset power range refers to the range of radio frequency wave power that is compatible with strong magnetic fields, second preset air pressure and frequency matching requirements. This preset power range can ensure high-density plasma generation while avoiding excessive ion energy or insufficient ionization.

[0096] The power of the radio frequency (RF) wave is crucial for balancing plasma density and ion energy. Insufficient RF power results in insufficient energy to drive the ionization of a large amount of helium, leading to a low plasma density and potentially insufficient irradiation flux to meet short-term cumulative flux requirements. Conversely, excessively high RF power can cause ion absorption energy exceeding 100 eV, resulting in severe physical sputtering of the tungsten substrate and potentially inducing plasma instability. In some implementations, the preset power range is 10 kW to 500 kW.

[0097] In this way, the frequency of the radio frequency wave matches the cyclotron resonance frequency of helium ions in a magnetic field environment, and the power of the radio frequency wave is within a preset power range. Thus, by controlling the radio frequency wave frequency to match the cyclotron resonance frequency and controlling the power of the radio frequency wave within a preset power range, the repair and growth of the tungsten wool layer can be completed quickly.

[0098] Please see Figure 4 In some embodiments, step 02 (based on a preset irradiation mode, processing the pre-injected helium gas to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range) includes:

[0099] 025: When the preset irradiation mode is the induced electric field assisted mode, control the helium gas pressure in the vacuum chamber where the first tungsten wall is located to be within the third preset pressure range;

[0100] 026: When the helium gas pressure is within the third preset pressure range, the central solenoid coil of the fusion device is excited to generate an induced electric field;

[0101] 027: Based on the induced electric field, helium gas is broken down to generate initial helium plasma;

[0102] 028: According to the preset auxiliary heating method, the initial helium plasma is processed to generate helium plasma and control the incident ion energy within the preset energy range.

[0103] Specifically, the induced electric field assisted mode refers to a plasma generation and irradiation method based on the principle of electromagnetic induction. It utilizes the existing central solenoid coil of the fusion device to excite the induced electric field to break down helium gas, and then enhances the ion energy through auxiliary heating. It has the characteristics of strong equipment compatibility and adaptability to complex magnetic field environments.

[0104] The third preset pressure range refers to the helium pressure range suitable for induced electric field breakdown and auxiliary heating. This third preset pressure range can ensure that the helium molecule density meets the induced electric field breakdown condition, while reducing collision losses of ions during movement, thus laying the foundation for precise control of ion energy. The third preset pressure range can be determined according to the induced electric field strength and auxiliary heating method.

[0105] The central solenoid coil is the core component in a fusion device used to generate a strong magnetic field and an induced electric field. It excites a changing magnetic field by switching the current on and off or changing the current intensity, thereby inducing a strong electric field. It is a key device for achieving the initial generation of helium plasma without the need for additional electrodes or wave sources.

[0106] The induced electric field refers to the electric field induced by the changing magnetic field generated by the central solenoid coil. Its strength is sufficient to break down helium gas and ionize it. It is the energy source for the initial generation of helium plasma. It has the characteristics of non-contact and full coverage, and can ensure the uniform distribution of plasma.

[0107] Initial helium plasma refers to the primary plasma formed after the induced electric field breaks down helium gas. The ion energy of initial helium plasma is low and cannot directly meet the requirements for inducing villous layer growth. It is necessary to further increase the energy through auxiliary heating.

[0108] The preset auxiliary heating method refers to the supplementary heating means used to enhance the energy of the initial helium plasma. It can input energy into the initial plasma to increase the kinetic energy of helium ions to a preset energy range of 20eV-100eV.

[0109] First, the vacuum chamber of the fusion device is evacuated to... Below Pa, interference from impurity gases is eliminated. The temperature of the first tungsten wall is slowly raised to 700℃-1300℃ and maintained stably using the device's built-in baking system or heat sink fluid heating system to meet the thermodynamic conditions for the formation of the fluff layer. High-purity helium is also injected into the vacuum chamber, and the helium pressure is stabilized within the third preset range through coordinated regulation by a gas flow controller and the vacuum pumping system.

[0110] Subsequently, the current control system of the central solenoid coil is activated, generating a changing magnetic field by altering the current intensity, which in turn induces a strong electric field. When the electric field intensity reaches the helium breakdown threshold, the helium is ionized, forming a uniformly distributed initial helium plasma.

[0111] Next, based on the existing equipment of the device, a preset auxiliary heating method is selected, the heating system is started and the power is set, energy is input into the initial helium plasma, helium plasma is generated and the incident ion energy is controlled within the preset energy range.

[0112] Thus, with the preset irradiation mode set to induced electric field assisted mode, the helium pressure in the vacuum chamber containing the first tungsten wall is controlled within a third preset pressure range. Next, with the helium pressure within this range, the central solenoid coil of the fusion device is excited, generating an induced electric field. Subsequently, based on this field, the helium gas is broken down, generating initial helium plasma. Finally, according to a preset auxiliary heating method, the initial helium plasma is processed to generate more helium plasma, and the incident ion energy is controlled within a preset energy range. In this way, under the ion cyclone wall processing mode, by controlling factors such as the helium pressure in the vacuum chamber, the induced electric field, and the preset auxiliary heating method, a stable in-situ generation of a tungsten wool layer and helium bubbles can be achieved on the first tungsten wall.

[0113] In some embodiments, the preset auxiliary heating method includes at least one of electron cyclotron resonance heating, ion cyclotron resonance heating, and neutral beam injection.

[0114] Specifically, electron cyclotron resonance heating refers to a plasma heating method based on the principle of electron cyclotron resonance. By emitting electromagnetic waves of a specific frequency, the frequency of the electromagnetic waves is matched with the cyclotron resonance frequency of electrons in the magnetic field of the device. After the electrons efficiently absorb the energy of the electromagnetic waves, they transfer energy through collisions with helium ions to achieve ion heating. It has the characteristics of high heating efficiency and precise energy transfer.

[0115] Ion cyclotron resonance heating refers to a heating method that uses radio frequency waves that match the cyclotron resonance frequency of helium ions to directly absorb radio frequency energy and increase kinetic energy. It does not require intermediate particles to transfer energy, has high energy utilization efficiency, and is suitable for scenarios that require rapid increase of ion energy.

[0116] Neutral beam injection refers to injecting a high-energy neutral particle beam into the initial helium plasma. The neutral particles undergo elastic collisions with the helium ions, transferring their kinetic energy to the helium ions, thereby increasing the energy of the helium ions. This heating method has the advantages of minimal plasma disturbance and adaptability to complex magnetic field environments.

[0117] Thus, the preset auxiliary heating methods include at least one of electron cyclotron resonance heating, ion cyclotron resonance heating, and neutral beam injection. This allows for the selection of one heating method to be used alone, or a combination of two or more, depending on the fusion device's equipment configuration, to adapt to different device hardware conditions and ensure heating efficiency and energy control precision.

[0118] In some embodiments, the tungsten fluff layer is a mesh structure formed by interwoven nanofibers, and the thickness of the tungsten fluff layer is [0.1 μm, 10 μm].

[0119] Specifically, nanofibers refer to tungsten fibers with diameters at the nanoscale. Their size effect endows the material with extremely high specific surface area and good flexibility. Unlike conventional micron-scale fibers, they can form a dense functional structure in a limited space and have excellent deformation ability to adapt to thermal expansion and contraction.

[0120] The interwoven network structure refers to the three-dimensional porous network formed by the mutual entanglement and overlapping of nanoscale tungsten fibers through atomic migration and recombination during the in-situ growth process, which combines porosity and structural integrity.

[0121] The thickness [0.1 μm, 10 μm] refers to the vertical distance range from the surface of the tungsten first wall to the top of the tungsten fluff layer. It should be noted that, based on numerous experiments, this range [0.1 μm, 10 μm] is clearly the optimal range for balancing functional performance and structural reliability in current fusion devices. If the fusion device is modified, this thickness can also be adjusted accordingly, and the generation method can still be the in-situ surface treatment method for the tungsten first wall provided in the embodiments of this application.

[0122] Thus, the tungsten fluff layer is a mesh structure formed by interwoven nanofibers, with a thickness of [0.1 μm, 10 μm]. The high specific surface area and porosity of this nanofiber mesh structure significantly improve the redeposition rate of tungsten atoms sputtered by impurity ions, effectively reducing net sputtering yield.

[0123] In some implementations, the helium bubble is located in the subsurface layer of the first tungsten wall beneath the tungsten velvet layer.

[0124] Specifically, the subsurface layer of the tungsten first wall refers to the shallower region below the surface of the tungsten first wall and inside the matrix, between the surface tungsten velvet layer and the deep matrix. The microstructure of this subsurface layer directly affects the surface mechanical stability and damage resistance of the tungsten first wall.

[0125] The helium bubble is located below the tungsten textural layer, which clearly defines the spatial relationship between the helium bubble layer and the tungsten textural layer. In this way, the helium bubble layer does not overlap with the tungsten textural layer, nor is it exposed on the first wall surface. Instead, it is located directly below the textural layer, forming a tightly connected two-layer structure that ensures functional coordination without interference between the two layers.

[0126] Thus, the helium bubbles are located in the subsurface layer of the first tungsten wall beneath the tungsten textural layer. The grain boundary pinning effect of the helium bubbles in this subsurface layer can suppress high-temperature recrystallization and grain growth. Combined with the thermal stress release function of the network structure of the tungsten textural layer, this ensures the crack formation rate of the first tungsten wall under thermal shock.

[0127] This application also provides a tungsten first wall, which is constructed based on the above method.

[0128] This application also provides a fusion device, which includes the aforementioned tungsten first wall.

[0129] Thus, the fusion device provided in this application includes a tungsten first wall, which comprises a tungsten wool layer and helium bubbles. The generated tungsten wool layer can capture impurity ions that bombard sputtered tungsten atoms, reducing the net sputtering yield of tungsten through a geometric redeposition effect and preventing helium plasma from being contaminated by tungsten ions. The generated helium bubbles can fix the subgrain boundaries or grain boundaries of tungsten through the Zener pinning effect, effectively suppressing recrystallization nucleation and grain growth at high temperatures, and maintaining the mechanical strength of the tungsten material. Furthermore, the tungsten wool layer and the helium bubble network together constitute a diffusion barrier for hydrogen isotopes, which can disrupt the continuous diffusion channels of hydrogen isotopes, reduce the steady-state permeation of hydrogen, deuterium, and tritium ions in the tungsten matrix, and ensure the safety of the fusion device. In addition, the tungsten wool layer also has low Young's modulus and foam-like properties, allowing it to expand and contract freely, releasing surface thermal stress under transient thermal loads and improving thermal shock resistance.

[0130] In this specification, the terms "specifically," "furthermore," "particularly," "understandably," etc., refer to specific features, structures, materials, or characteristics described in connection with embodiments or examples that are included in at least one embodiment or example of this application. 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.

[0131] Any process or method description in the flowchart or otherwise herein can be understood as representing a module, segment, or portion of executable request code comprising one or more steps for implementing a particular logical function or process, and the scope of the preferred embodiments of this application includes additional implementations in which functions may be performed not in the order shown or discussed, including substantially simultaneously or in reverse order according to the functions involved, as should be understood by those skilled in the art to which embodiments of this application pertain.

[0132] Although embodiments of this application have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting this application. Those skilled in the art can make changes, modifications, substitutions and variations to the above embodiments within the scope of this application.

Claims

1. A method for in-situ surface treatment of the first tungsten wall of a fusion device, characterized in that, The method includes: The tungsten first wall is heated to a preset temperature range, which is [700℃, 1300℃]; Based on a preset irradiation mode, the pre-injected helium gas is processed to generate helium plasma and the energy of the incident ions reaching the first tungsten wall is controlled to be within a preset energy range, which is [20eV, 100eV]. The preset irradiation mode includes DC glow discharge mode, ion cyclone wall processing mode and induced electric field assisted mode. According to the helium plasma, the tungsten first wall within the preset temperature range is irradiated until the cumulative helium ion flux of the tungsten first wall meets a preset condition, so as to generate a tungsten wool layer and helium bubbles in situ on the tungsten first wall. The preset condition is that the cumulative helium ion flux is greater than The tungsten fluff layer is a mesh structure formed by interwoven nanofibers, and the thickness range of the tungsten fluff layer is [0.1μm, 10μm]. The helium bubble is located in the subsurface layer of the first tungsten wall below the tungsten fluff layer.

2. The method according to claim 1, characterized in that, The process of treating pre-injected helium gas based on a preset irradiation mode to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range includes: When the preset irradiation mode is the DC glow discharge mode, the helium pressure in the vacuum chamber where the tungsten first wall is located is controlled to be within the first preset pressure range. When the helium gas pressure is within the first preset pressure range, the helium gas is processed according to the preset DC voltage applied to the first tungsten wall to generate the helium plasma and control the incident ion energy to be within the preset energy range, wherein the first tungsten wall is a cathode.

3. The method according to claim 1, characterized in that, The process of treating pre-injected helium gas based on a preset irradiation mode to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range includes: When the preset irradiation mode is the ion cyclone wall treatment mode, under a magnetic field environment with a preset magnetic field strength, the helium pressure in the vacuum chamber where the tungsten first wall is located is controlled to be within the second preset pressure range. When the helium gas pressure is within the second preset pressure range, the helium gas is processed according to the radio frequency wave emitted by the ion cyclotron resonance heating antenna of the fusion device to generate the helium plasma and control the incident ion energy to be within the preset energy range.

4. The method according to claim 3, characterized in that, The frequency of the radio frequency wave matches the cyclotron resonance frequency of helium ions in the magnetic field environment, and the power of the radio frequency wave is within a preset power range.

5. The method according to claim 1, characterized in that, The process of treating pre-injected helium gas based on a preset irradiation mode to generate helium plasma and controlling the incident ion energy of the helium plasma reaching the first tungsten wall to be within a preset energy range includes: When the preset irradiation mode is the induced electric field assisted mode, the helium pressure in the vacuum chamber where the tungsten first wall is located is controlled to be in the third preset pressure range. When the helium gas pressure is within the third preset pressure range, the central solenoid coil of the fusion device is excited to generate an induced electric field. Based on the induced electric field, the helium gas is broken down to generate an initial helium plasma; The initial helium plasma is processed according to a preset auxiliary heating method to generate the helium plasma and control the energy of the incident ions to be within the preset energy range.

6. The method according to claim 5, characterized in that, The preset auxiliary heating method includes at least one of electron cyclotron resonance heating, ion cyclotron resonance heating, and neutral beam injection.

7. A tungsten first wall, characterized in that, The first tungsten wall is constructed based on the method described in any one of claims 1-6.

8. A fusion device, characterized in that, The fusion device includes the tungsten first wall as described in claim 7.

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