CN111257351A - Irradiation water-cooling sample platform - Google Patents

Abstract

The invention discloses an irradiation water-cooling sample stage, which comprises a sample stage main body, wherein a sample placing stage is arranged at the top of the sample stage main body, a sample support base is arranged at the bottom of the sample stage main body, and a sample protective sleeve is arranged outside the sample stage main body; the lower part of the sample table main body is provided with a water inlet and a water outlet, and the water inlet is positioned above the water outlet; a fixing ring is arranged inside the sample table main body; the water outlet end is connected with a bias connection wire. The invention can be used for researching the damage characteristic behavior of plasma material surface treatment under the condition of high-power irradiation. And experimental basis is provided for the water cooling test of the ITER divertor.

Description

Irradiation water-cooled sample stage

technical field

The invention relates to a feasibility experiment for simulating the damage effect of a first wall and a water-cooled divertor material under the conditions of high temperature and strong particle bombardment in the technical field of nuclear fusion tokamak by simulating the magnetic confinement nuclear fusion reaction process device.

Background technique

With the exhaustion of traditional fossil fuels and the increasingly serious environmental problems, the development of new energy sources is imminent. The nuclear fusion that appeared in the last century has brought a revolution to solving the energy problem. For now, the development of fusion energy has been unstoppable. In order to better realize technology sharing, seven member countries including China, Russia, the United States, and France jointly bear the research and development expenses, and officially launched the "International Thermonuclear Experimental Reactor Project", the ITER project. In the fusion environment, as the first wall material directly facing the plasma and the divertor material for removing impurities such as He ash, it will be irradiated from the fusion reactants (deuterium, tritium) and products (helium, neutrons) . The generated impurities are easily transported to the plasma core under the strong electromagnetic field environment, resulting in the extinction of the fusion reactor. Therefore, it is of great scientific significance and application value to carry out research on plasma-oriented materials and plasma interactions in a fusion environment. In the present invention, a self-designed high-power radio frequency ion source is used to generate high-density plasma, so as to simulate the irradiation environment where the plasma-facing material is located, and the water-cooled sample holder can reduce the surface temperature of the plasma-facing material below 1000K, thereby The damage behavior of tungsten and its alloys under He ⁺ or H ⁺ /D ⁺ irradiation was systematically studied, providing effective theoretical and experimental data support for the ITER program.

For nuclear fusion, the key to its stable operation is to find materials that can withstand strong electromagnetic fields, high-energy particle bombardment and stable operation under high temperature conditions. Therefore, it is particularly important to study the unique radiation damage mechanism of the existing key fusion reactor outsourcing materials such as beryllium, molybdenum, tungsten or carbon. As we all know, in order to ensure the stable operation of the fusion reactor, for the first wall material and the divertor target plate material wrapped in the core, the copper tube is welded to the tungsten or beryllium back target plate and the cooling water is introduced to make the surface temperature. reduced, so that the plasma-oriented material can operate stably under high temperature and strong particle bombardment conditions. Therefore, this design reduces the temperature of the tested sample placed in the plasma environment to below 1000K through the self-invented irradiation water-cooled sample stage according to the relevant parameters during the actual operation of the fusion reactor. Based on this, the present invention designs an experimental device for an irradiation water-cooled sample platform, the main purpose of which is to simulate the changes in the performance and structure of the water-cooled material itself in the low-energy and high-current environment during the actual operation of the fusion reactor. The design of the device has not been reported so far.

SUMMARY OF THE INVENTION

The purpose of the present invention is to provide a water-cooled sample stage that can be used to test the performance of samples under high-power and low-temperature irradiation conditions, which can simulate the irradiation damage behavior of plasma materials under the operating environment of a nuclear fusion reactor tokemak.

For realizing the above-mentioned purpose of the invention, the technical scheme adopted in the present invention is:

An irradiation water-cooled sample stage device includes a sample stage main body, a sample placement stage is arranged on the top of the sample stage main body, a sample holder base is arranged at the bottom of the sample stage main body, and a sample is arranged on the outside of the sample stage main body. protective case;

The lower part of the main body of the sample stage is provided with a water inlet and a water outlet, and the water inlet is located above the water outlet; the inside of the main body of the sample stage is provided with a fixing ring;

The water outlet end is connected with the bias wiring.

Further, one end of the water inlet is connected to the water inlet pipe, and the other end is connected to the water inlet port.

Further, the water inlet is fixed at the coaxial center position of the main body of the sample stage by a fixing ring, and the distance between the water outlet (top) of the water inlet and the sample placing table is 10 mm.

Further, one end of the water outlet is connected to the water outlet pipe, and the other end is connected to the water outlet port.

Further, the inside of the main body of the sample stage is provided with a fixing ring for fixing the outlet end of the water inlet.

Further, the fixing ring fixes the water inlet pipe at the central position of the main body of the sample stage.

Further, the water outlet pipe is welded on the side of the sample holder at a position 80 mm away from the sample placing table, so as to ensure the normal use of the water circulation system.

Further, the main body of the sample stage is communicated with the water inlet and the water outlet respectively; the water enters the main body of the sample stage through the water inlet through the water inlet pipe, and then flows out through the water outlet.

Further, the bias line interface is placed at the water outlet end at a distance of 10mm from the water inlet interface.

Further, the sample placing platform is connected with the sample to be tested, and the water outlet end is connected with a bias voltage source through a bias voltage wire.

Further, the sample holder base is fixedly connected with the main body of the sample stage.

Further, the sample holder base is tightly connected with the lower end of the main body of the sample stage through threads to ensure insulation from the vacuum chamber.

Further, the bottom of the sample holder base is provided with a boron nitride base, the sample holder base is fixedly connected with the boron nitride base, and the fixed connection is in a threaded connection.

Further, the main body of the sample stage, including the sample placing stage, the water inlet, the water outlet, and the fixing ring, is made of metal molybdenum material.

Further, the sample protective cover and the sample holder base are made of boron nitride ceramic material with good high temperature thermal stability.

The main structure of the sample protective sleeve is a cylinder, the inner diameter of the protective sleeve is consistent with the outer diameter of the main body of the sample stage, the wall thickness is 3mm, and a 10mm*10mm square hole is opened at the sample placement stage, so that the sample to be tested can be exposed to plasma environment, while the rest is protected by a boron nitride ceramic cover.

Combining the above technical solutions, the invention can realize the research on the damage characteristic behavior of the surface treatment of the plasma material under the condition of high-power irradiation. Provide experimental basis for the water cooling test of ITER divertor. Under the irradiation condition of low energy and high current intensity (1×10 ²² ions/m ² -1×10 ²³ ions/m ² ) provided by the invention, the tested sample has the following beneficial effects after water cooling treatment:

Using a water-cooled sample holder, the surface temperature of the material can be reduced to below 1000K under a low-energy and high-current irradiation device. In the actual operation process of the fusion device, the radiation damage characteristics of the first wall and the divertor material at the actual operating temperature can be effectively studied. Because of its high temperature stability and other characteristics, W material is considered to be the most promising divertor target material at present. The W sample to be tested is placed on the upper surface of the water-cooled sample stage, and the sample stage is cooled by cooling water. Atomic force microscopy was used to analyze the morphological changes produced by the surface structure of the W sample and compared with the irradiated sample without water cooling. The experiment found that under the same incident ion energy conditions, the surface of the sample had large area bubbles after the water-cooling cycle treatment. Under the same experimental conditions, without the water-cooling cycle treatment, when the surface temperature exceeded 1000K, the sample surface had obvious bubbles. Compared with the treatment conditions with cooling circulating water, the generation of nano-filament structure is completely different from the surface microstructure of the sample, and the phenomenon has never been reported before, which proves the innovation of the present invention.

Description of drawings

Fig. 1 is the schematic diagram of the main structure of the irradiation sample stage and the schematic diagram of the base of the sample stage;

Fig. 2 is the SEM image of the sample irradiation, wherein a is the surface of the sample after irradiation treatment of the water-cooled sample stage, and b is the surface of the sample that is not irradiated by the water-cooled sample;

In the picture: 1. Water inlet, 2. Water outlet, 3. Sample placing table, 4. Bias line interface, 5. Main body of sample table, 6. Sample holder base, 7. Water inlet port, 8. Water outlet port, 9 , Fixing ring, 10, Boron nitride base, 11, Sample protective sleeve, 12, Inlet pipe, 13, Outlet pipe.

Detailed ways

The specific implementation of the present invention is further described as follows with reference to the accompanying drawings.

A water-cooled sample stage for an irradiation cooling device includes a sample stage main body 5, a sample placing stage 3 is arranged on the top of the sample stage main body 5, and a sample holder base 10 is arranged at the bottom of the sample stage main body 5, so The outside of the sample stage main body 5 is provided with a sample protective cover 11. The lower part of the sample stage main body 5 is provided with a water inlet 1 and a water outlet 2. The water inlet 1 is located above the water outlet 2. The inside is provided with a fixing ring for fixing the water inlet pipe; the water outlet 2 is connected with the bias wiring;

The main body 5 of the sample stage is made of a high-temperature stable metal molybdenum material, that is, a molybdenum sample stage, and the water inlet 1 is made of a high-temperature stable metal molybdenum material. One end of 1 is connected to the water inlet pipe 12, and the other end is connected to the white steel water inlet port 7. The circular molybdenum plate is welded and sealed with the lower end of the sample stage main body 5, and the outlet end of the water inlet 1 is fixed to the sample stage main body through the fixing ring 9. 5, and leave a 10mm gap with the upper sample placing table 3 to ensure that the circulating water can be injected through the water inlet pipe 12 and sprayed on the lower surface of the sample placing table 3. The lower end of the water inlet is connected with the white steel water inlet port 7, so that the circulating water is injected from the lower end of the sample stage main body 5 and sprayed on the upper surface of the sample stage, so as to achieve the cooling effect;

The water outlet 2 is made of metal molybdenum material, one end of the water outlet 2 is connected to the water outlet pipe 12, the other end is connected to the white steel water outlet 8, and one end of the water outlet 2 is connected to the side of the main body 5 of the sample stage. It is welded at the opening 80mm away from the upper surface, and the other end is connected to the water outlet interface 8 to ensure that the cooling water can flow out continuously and stably.

The sample placing table 3 is placed on the top of the main body 5 of the sample table, and is made of metal molybdenum material. The surface is polished and connected to the sample to be tested to ensure that the lower surface of the sample to be tested is fully in contact with the upper surface of the sample holder placing table 3. , thereby improving the cooling efficiency.

The bias line interface 4 is placed at the water inlet end of the water outlet 2, and the water outlet 2 is connected to the bias source through a bias wire. When the DC negative bias source is turned on, it can attract ions to bombard the surface of the sample, simulating Radiation damage experiments.

The whole body of the sample protective cover 11 is made of boron nitride ceramic material with good thermal stability at high temperature, with a total length of 100 mm, a diameter of 30 mm, and a wall thickness of 3 mm. A 10mm*10mm square hole is opened on the upper surface of the sample protective cover 11 so that the sample to be tested can be completely exposed to the plasma environment, and the rest is blocked by the protective cover to protect the rest of the sample stage main body 5 from bombardment by high-energy particles, thereby causing Water-cooled sample holder damage.

The sample holder base 6 is made of boron nitride ceramic material with a diameter of 60 mm, and is tightly connected with the lower end of the water-cooled sample stage main body 5 through threads. The bottom of the sample holder base 6 is tightly connected with the boron nitride base 10 through threads. At the same time, it is ensured that the main body 5 of the water-cooled sample stage can be stably placed at the center of the ion source, thereby ensuring complete insulation between the main body 5 of the water-cooled sample stage and the vacuum chamber.

The working principle of the present invention is as follows: first, one end of the water inlet port 7 is connected with the water inlet 1, and the other end is connected with the white steel water inlet pipe 12, and the water inlet pipe 11 is connected with the water cooling circulation system. One end of the water outlet 8 is connected to the water outlet 2 and the other end is connected to the white steel water outlet pipe 13 . The sample holder base 6 and the lower end of the sample main body 5 are screwed together and placed in the vacuum chamber. Place the sample to be tested in the center of the sample placing table 3, and cover the sample protective cover 11 on the outer surface of the main body 5 of the water-cooled sample stage from top to bottom, only to ensure that the sample to be tested is exposed to the plasma area. The bias interface 4 is connected to the sample stage main body 5 . Open the water cooling circulation system, and the cooling efficiency can be adjusted by adjusting the water intake. Turn on the bias power supply, and the generated high-density plasma will finally reach the surface of the tested sample through directional attraction for irradiation experiments, and the temperature will reach the predetermined experimental conditions by adjusting the water inlet pressure.

The W sample to be tested is placed on the upper surface of the water-cooled sample stage, the sample stage is cooled by cooling water, and the W sample is irradiated by the self-developed irradiation device (publication number CN104157321B) to make the surface structure change under low temperature conditions. Scanning electron microscopy (SEM) was used to analyze the topographic changes produced by the surface structure of the W samples and compared with the irradiated samples without water cooling. The test conditions are the incident ion energy conditions: 50ev, power 5kw, energy flow 1×10 ²² ions/m ² , the temperature of the sample treated with water cooling cycle is 800K, and the temperature without water cooling cycle treatment is 1300K; Under the same incident ion energy condition (50ev), there is a large area of bubbles on the surface of the sample after water cooling cycle treatment (as shown in Figure 2(a)). Under the same experimental conditions, without water cooling cycle treatment, when the surface temperature exceeds 1300K, the surface of the sample has obvious nano-filament structure (as shown in Figure 2(b)). Compared with the treatment conditions with cooling circulating water, the microstructure of the sample surface is completely different, and the phenomenon has never been reported before, which proves the innovation of the present invention.

The above description is only a preferred embodiment of the present invention, but the protection scope of the present invention is not limited to this. The equivalent replacement or modification of its inventive concept shall be included within the protection scope of the present invention.

Claims (10)

1. An irradiation water-cooling sample platform which is characterized in that: the sample table comprises a sample table main body, wherein a sample placing table is arranged at the top of the sample table main body, a sample support base is arranged at the bottom of the sample table main body, and a sample protective sleeve is arranged outside the sample table main body;

the lower part of the sample table main body is provided with a water inlet and a water outlet, and the water inlet is positioned above the water outlet; a fixing ring is arranged inside the sample table main body;

the water outlet is connected with a bias connection wire.

2. The irradiation water-cooled sample stage according to claim 1, characterized in that: one end of the water inlet is connected with the water inlet pipe, and the other end of the water inlet is connected with the water inlet interface.

3. The irradiation water-cooled sample stage according to claim 1, characterized in that: one end of the water outlet is connected with the water outlet pipe, and the other end of the water outlet is connected with the water outlet interface.

4. The irradiation water-cooled sample stage according to claim 2, characterized in that: the inside of sample platform main part is equipped with the solid fixed ring that is used for the water outlet end of fixed water inlet.

5. The irradiation water-cooled sample stage according to claim 3, wherein: the water inlet pipe is fixed at the center of the sample table main body by the fixing ring.

6. The irradiation water-cooled sample stage according to claim 1, characterized in that: the sample support base is fixedly connected with the sample table main body.

7. The irradiation water-cooled sample stage according to claim 1, characterized in that: the sample placing table is connected with a sample to be measured, and the water outlet end is connected with a bias voltage source through a bias voltage wiring.

8. The irradiation water-cooled sample stage according to claim 1, characterized in that: and a boron nitride base is arranged at the bottom of the sample support base.

9. The irradiation water-cooled sample stage according to claim 1, characterized in that: the sample table main body is made of a metal molybdenum material.

10. The irradiation water-cooled sample stage according to claim 1, characterized in that: the sample protective sleeve and the sample support base are made of boron nitride ceramic materials.

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