CN111257351B - Irradiation water-cooling sample platform - Google Patents
Irradiation water-cooling sample platform Download PDFInfo
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- CN111257351B CN111257351B CN202010086563.2A CN202010086563A CN111257351B CN 111257351 B CN111257351 B CN 111257351B CN 202010086563 A CN202010086563 A CN 202010086563A CN 111257351 B CN111257351 B CN 111257351B
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- 238000001816 cooling Methods 0.000 title claims abstract description 29
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 109
- 239000000463 material Substances 0.000 claims abstract description 27
- 230000001681 protective effect Effects 0.000 claims abstract description 15
- 229910052582 BN Inorganic materials 0.000 claims description 10
- PZNSFCLAULLKQX-UHFFFAOYSA-N Boron nitride Chemical compound N#B PZNSFCLAULLKQX-UHFFFAOYSA-N 0.000 claims description 10
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 claims description 9
- 229910052750 molybdenum Inorganic materials 0.000 claims description 9
- 239000011733 molybdenum Substances 0.000 claims description 9
- 229910052751 metal Inorganic materials 0.000 claims description 6
- 239000002184 metal Substances 0.000 claims description 6
- 229910010293 ceramic material Inorganic materials 0.000 claims description 4
- 239000007787 solid Substances 0.000 claims description 2
- 238000012360 testing method Methods 0.000 abstract description 4
- 238000004381 surface treatment Methods 0.000 abstract description 2
- 230000004927 fusion Effects 0.000 description 18
- 238000002474 experimental method Methods 0.000 description 6
- 150000002500 ions Chemical class 0.000 description 6
- 238000011160 research Methods 0.000 description 6
- 229910000831 Steel Inorganic materials 0.000 description 5
- 230000008859 change Effects 0.000 description 5
- 239000010959 steel Substances 0.000 description 5
- 239000000498 cooling water Substances 0.000 description 4
- 239000002245 particle Substances 0.000 description 4
- 230000006399 behavior Effects 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 description 3
- 239000010937 tungsten Substances 0.000 description 3
- 229910052721 tungsten Inorganic materials 0.000 description 3
- 229910052790 beryllium Inorganic materials 0.000 description 2
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000005672 electromagnetic field Effects 0.000 description 2
- 239000012535 impurity Substances 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- 230000001678 irradiating effect Effects 0.000 description 2
- 239000005022 packaging material Substances 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 1
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000005187 foaming Methods 0.000 description 1
- 239000002803 fossil fuel Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000000376 reactant Substances 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 238000001878 scanning electron micrograph Methods 0.000 description 1
- 230000009897 systematic effect Effects 0.000 description 1
- 229910052722 tritium Inorganic materials 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01L—CHEMICAL OR PHYSICAL LABORATORY APPARATUS FOR GENERAL USE
- B01L9/00—Supporting devices; Holding devices
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/28—Preparing specimens for investigation including physical details of (bio-)chemical methods covered elsewhere, e.g. G01N33/50, C12Q
- G01N1/44—Sample treatment involving radiation, e.g. heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/25—Maintenance, e.g. repair or remote inspection
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/10—Nuclear fusion reactors
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- Chemical & Material Sciences (AREA)
- Health & Medical Sciences (AREA)
- Immunology (AREA)
- Engineering & Computer Science (AREA)
- Biochemistry (AREA)
- General Health & Medical Sciences (AREA)
- General Physics & Mathematics (AREA)
- Life Sciences & Earth Sciences (AREA)
- Pathology (AREA)
- Analytical Chemistry (AREA)
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- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma Technology (AREA)
- Sampling And Sample Adjustment (AREA)
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
Technical Field
The invention relates to a feasibility experiment device which can simulate 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 magnetic confinement nuclear fusion reaction process in the technical field of nuclear fusion tokomak.
Background
With the exhaustion of traditional fossil fuels and increasingly serious environmental problems, the development of new energy sources is urgently needed. Nuclear fusion, which has emerged in the last century, has brought an innovation for solving the energy problem, and the development of fusion energy has been overwhelming at present. In order to better realize the technology sharing, 7 member countries including Russia, America, Law and the like in China commonly bear research and development cost, and formally develop an international thermonuclear fusion experimental reactor plan, namely an ITER plan internationally. Under the fusion environment, as a first wall material directly facing to plasma and a divertor material for removing impurities such as He ash, etc., the first wall material and the divertor material are irradiated by fusion reactants (deuterium and tritium) and products (helium and neutron). The generated impurities are easy to transport to the plasma core under the strong electromagnetic field environment, thereby causing the extinguishing of the fusion reactor. Therefore, the research of plasma interaction in plasma materials and fusion environments is developed, and the research has important scientific significance and application value. In the invention, the high-density plasma is generated by utilizing the independently designed high-power radio frequency ion source, thereby simulating the orientationThe temperature of the surface of the plasma-facing material can be reduced to below 1000K by utilizing the water-cooled sample holder in the irradiation environment of the plasma material, so that the systematic research on the He of tungsten and alloy materials thereof+Or H+/D+And damage behaviors under irradiation conditions provide effective theoretical and experimental data support for the ITER plan.
For nuclear fusion, the key of stable operation is to find out the material of the fusion reactor capable of bearing strong electromagnetic field, high-energy particle bombardment and stable operation under high temperature condition. Therefore, aiming at the existing critical fusion reactor outer packaging materials such as beryllium, molybdenum, tungsten or carbon, the research on the specific radiation damage mechanism of the fusion reactor outer packaging materials is particularly important. As is known, in order to ensure the stable operation of the fusion reactor, the first wall material wrapped by the reactor core and the target plate material of the divertor are both in a mode of welding a copper pipe on a tungsten or beryllium back target plate and introducing cooling water, so that the surface temperature of the first wall material and the target plate material is reduced, and the plasma-oriented material can stably operate under the conditions of high temperature and strong particle bombardment. Therefore, according to relevant parameters in the actual operation process of the fusion reactor, the temperature of a measured sample placed in a plasma environment is reduced to be below 1000K through the independently invented irradiation water-cooled sample stage. Based on the experiment, the invention designs the irradiation water-cooling sample stage experimental device, and the main purpose of the experimental device is to simulate the change of the performance and the structure of the water-cooling material in the low-energy high-current strong environment in the actual operation process of the fusion reactor. The design of the device has not been reported so far.
Disclosure of Invention
The invention aims to provide a water-cooled sample stage for testing the performance of a sample under a high-power low-temperature irradiation condition, which can simulate the irradiation damage behavior research of a plasma material under a nuclear fusion reactor Tokamak running environment.
In order to achieve the purpose of the invention, the technical scheme adopted by the invention is as follows:
an irradiation water-cooling sample stage device comprises a sample stage main body, wherein a sample placing table 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.
Furthermore, 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.
Furthermore, the water inlet is fixed at the coaxial central position of the sample table main body through a fixing ring, and the distance between the water outlet end (top end) of the water inlet and the sample placing table is 10 mm.
Furthermore, 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.
Furthermore, a fixing ring for fixing the outlet end of the water inlet is arranged in the sample table main body.
Furthermore, the water inlet pipe is fixed at the center of the sample table main body by the fixing ring.
Furthermore, the water outlet pipe is welded at the position, 80mm away from the sample placing table, of the side surface of the sample support, so that the normal use of the water circulation system is ensured.
Furthermore, the sample table main body is respectively communicated with the water inlet and the water outlet; water enters the sample table main body through the water inlet pipe through the water inlet and then flows out through the water outlet.
Furthermore, the bias line interface is arranged at the water outlet end and is 10mm away from the water inlet interface.
Furthermore, 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.
Furthermore, the sample support base is fixedly connected with the sample table main body.
Furthermore, the sample support base is tightly connected with the lower end of the sample table main body through threads, so that the insulation between the sample support base and the vacuum chamber is ensured.
Further, the bottom of the sample support base is provided with a boron nitride base, the sample support base is fixedly connected with the boron nitride base, and the fixed connection mode is threaded connection.
Furthermore, the sample table main body comprises a sample placing table, a water inlet, a water outlet and a fixing ring, and is made of a metal molybdenum material.
Furthermore, the sample protective sleeve and the sample support base are made of boron nitride ceramic materials with good high-temperature thermal stability.
The sample protective sheath main part structure be the cylinder, its protective sheath internal diameter keeps unanimous with sample platform main part external diameter, the wall thickness is 3mm, places platform department at the sample and opens 10mm square holes, makes the sample of being surveyed can expose under the plasma environment, and the rest is then protected by boron nitride ceramic cover.
By combining the technical scheme, the invention can realize the research on the damage characteristic behavior of the plasma material surface treatment under the high-power irradiation condition by using the temperature. And experimental basis is provided for the water cooling test of the ITER divertor. The invention provides a high current intensity (1 multiplied by 10) at low energy22ions/m2-1×1023ions/m2) Under the irradiation condition, the tested sample has the following beneficial effects after water cooling treatment:
the water-cooled sample holder can reduce the surface temperature of the material to below 1000K under a low-energy high-current strong irradiation device. The irradiation damage characteristic of the first wall and the divertor material at the actual operation temperature can be effectively researched in the actual operation process of the fusion device. The W material is considered to be the most promising target plate material for divertors because of its high temperature stability. A W sample to be measured is placed on the upper surface of a water-cooled sample stage, the sample stage is cooled by introducing cooling water, the surface structure of the W sample is changed under a low-temperature condition by irradiating the W sample by using an irradiation device, the appearance change generated by the surface structure of the W sample is analyzed by a Scanning Electron Microscope (SEM) and an atomic force microscope, and the appearance change is compared with the irradiated sample without water cooling. Experiments show that under the same incident ion energy condition, the sample surface has large-area foaming condition after water cooling circulation treatment, and under the same experiment condition, water cooling circulation treatment is not added, when the surface temperature exceeds 1000K, the sample surface has obvious generation of nano filamentous structures, compared with the treatment condition with cooling circulation water, the microstructure of the sample surface is completely different, and the generated phenomenon is not reported, thereby proving the innovation of the invention.
Drawings
FIG. 1 is a schematic diagram of the main structure of an irradiation sample stage and a schematic diagram of a base of the sample stage;
FIG. 2 is an SEM image of sample irradiation, wherein a is the sample surface after water-cooled sample stage irradiation treatment, and b is the sample surface after non-water-cooled sample irradiation treatment;
in the figure: 1. the water inlet, 2, the delivery port, 3, the sample is placed the platform, 4, the bias voltage line interface, 5, sample platform main part, 6, the sample holds in the palm the base, 7, the interface of intaking, 8, the interface of going out water, 9, solid fixed ring, 10, boron nitride base, 11, sample protective sheath, 12, inlet tube, 13, the outlet pipe.
Detailed Description
The invention is further described below with reference to the accompanying drawings.
A water-cooling sample stage for an irradiation cooling device comprises a sample stage main body 5, wherein a sample placing table 3 is arranged at the top of the sample stage main body 5, a sample support base 10 is arranged at the bottom of the sample stage main body 5, a sample protective sleeve 11 is arranged outside the sample stage main body 5, a water inlet 1 and a water outlet 2 are arranged at the lower part of the sample stage main body 5, the water inlet 1 is positioned above the water outlet 2, and a fixing ring for fixing a water inlet pipe is arranged inside the sample stage main body 5; the water outlet 2 is connected with a bias connection wire; .
The sample table main body 5 is made of a high-temperature stable metal molybdenum material, namely a molybdenum sample table, the water inlet 1 is made of a high-temperature stable metal molybdenum material, one end of the water inlet 1 is connected with a water inlet pipe 12, the other end of the water inlet 1 is connected with a white steel water inlet interface 7, the water inlet is welded and sealed with the lower end of the sample table main body 5 through a circular molybdenum plate, the outlet end of the water inlet 1 is fixed at the central position of the sample table main body 5 through a fixing ring 9, a 10mm gap is reserved between the outlet end of the water inlet 1 and the upper end sample placing table 3, and 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 a white steel water inlet interface 7, so that circulating water is injected from the lower end of the sample stage main body 5 and is sprayed on the upper surface of the sample stage, and the cooling effect is achieved;
the water outlet 2 is made of metal molybdenum, one end of the water outlet 2 is connected with the water outlet pipe 12, the other end of the water outlet 2 is connected with the white steel water outlet port 8, one end of the water outlet 2 is welded with an opening, 80mm away from the upper surface, of the side of the sample table main body 5, the other end of the water outlet 2 is connected with the water outlet port 8, and therefore cooling water can flow out continuously and stably.
The sample placing table 3 is placed on the top of the sample table main body 5 and made of metal molybdenum materials, the surface of the sample placing table is polished and connected with a sample to be measured, the lower surface of the sample to be measured is guaranteed to be in full contact with the upper surface of the sample supporting and placing table 3, and therefore cooling efficiency is improved.
The bias line interface 4 is placed at the water inlet end of the water outlet 2, the water outlet 2 is connected with a bias voltage source through a bias voltage wiring, when the direct current negative bias voltage source is started, ions can be attracted to bombard the surface of a sample, and an irradiation damage experiment is simulated.
The sample protective sleeve 11 is made of boron nitride ceramic materials with good high-temperature thermal stability, the total length is 100mm, the diameter is 30mm, and the wall thickness is 3 mm. The upper surface of the sample protective sleeve 11 is provided with a 10 mm-10 mm square hole, so that a measured sample can be completely exposed in a plasma environment, the rest part of the sample protective sleeve is shielded by the protective sleeve, and the rest part of the sample table main body 5 is protected from high-energy particle bombardment, so that the water-cooled sample support is damaged.
The sample support base 6 is made of a boron nitride ceramic material with the diameter of 60mm and is tightly connected with the lower end of the water-cooling sample table main body 5 through threads. The bottom of the sample holder base 6 is tightly connected with the boron nitride base 10 through threads. Meanwhile, the water-cooled sample stage main body 5 can be stably arranged at the center of the ion source, so that complete insulation between the water-cooled sample stage main body 5 and the vacuum cavity is ensured.
The working principle of the invention is that firstly, one end of a water inlet interface 7 is connected with a water inlet 1, the other end is connected with a white steel water inlet pipe 12, and the water inlet pipe 11 is connected with a water cooling circulation system. One end of the water outlet port 8 is connected with the water outlet 2, and the other end is connected with the white steel water outlet pipe 13. The sample support base 6 is screwed with the lower end of the sample main body 5 through threads and is placed in the vacuum cavity. The sample to be measured is placed in the center of the sample placing table 3, and the sample protective sleeve 11 is sleeved on the outer surface of the water-cooling sample table main body 5 from top to bottom, so that the sample to be measured is only ensured to be exposed in the plasma area. The bias interface 4 is connected with the sample stage body 5. And the water cooling circulation system is opened, and the cooling efficiency can be adjusted by adjusting the water inflow. And starting a bias power supply, enabling the generated high-density plasma to finally reach the surface of the sample to be detected through directional attraction to carry out an irradiation experiment, and enabling the temperature to reach a preset experimental condition through regulating the water inlet pressure.
A W sample to be measured is placed on the upper surface of a water-cooled sample stage, the sample stage is cooled by introducing cooling water, the surface structure of the W sample is changed under a low-temperature condition by irradiating the W sample by using an independently developed irradiation device (publication number CN104157321B), the appearance change generated by the surface structure of the W sample is analyzed by a Scanning Electron Microscope (SEM), and the appearance change is compared with the sample irradiated without water cooling. The test conditions are incident ion energy conditions: 50ev, power 5kw, energy flow 1X 1022ions/m2The temperature of the water-cooling circulation processing sample is 800K, and the temperature of the water-cooling circulation processing without water is 1300K; it was found that the surface of the sample was subjected to water cooling cycle treatment under the same incident ion energy condition (50ev) (as shown in fig. 2 (a)). Under the same experimental conditions, when the surface temperature exceeds 1300K without water cooling circulation treatment, obvious generation of nano filamentous structures on the surface of the sample is generated (as shown in figure 2 (b)). Compared with the treatment condition with the cooling circulating water, the microstructure of the surface of the sample is completely different, and the generated phenomenon is not reported, thereby proving the innovation of the invention.
The above description is only for the preferred embodiment of the present invention, but the scope of the present invention is not limited thereto, and any person skilled in the art should be able to cover the technical scope of the present invention and the equivalent alternatives or modifications according to the technical solution and the inventive concept of the present invention within the technical scope of the present invention.
Claims (6)
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 holder base is arranged at the bottom of the sample table main body, a boron nitride base is arranged at the bottom of the sample holder base, 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 inlet is fixed at the coaxial central position of the sample table main body through a fixing ring;
the water outlet is connected with a bias connection wire;
the sample support base is in threaded connection with the sample table main body;
the upper surface of the sample protective sleeve is provided with a 10 mm-10 mm square hole;
the sample table main body is made of a metal molybdenum material; the sample protective sleeve and the sample support base are made of boron nitride ceramic materials.
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 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.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202010086563.2A CN111257351B (en) | 2020-02-11 | 2020-02-11 | Irradiation water-cooling sample platform |
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| CN202010086563.2A CN111257351B (en) | 2020-02-11 | 2020-02-11 | Irradiation water-cooling sample platform |
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| CN114446495A (en) * | 2022-01-18 | 2022-05-06 | 大连理工大学 | Inverted sample table for collecting fallen objects in plasma zone |
| CN115193503B (en) * | 2022-07-21 | 2023-11-14 | 大连理工大学 | Cooling experiment table capable of effectively relieving heat concentration of samples in radio frequency ion source |
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| CN105021469A (en) * | 2015-07-10 | 2015-11-04 | 中山大学 | In-situ mechanical property testing device of nuclear material in high temperature irradiation simulation environment |
| CN205641719U (en) * | 2016-04-27 | 2016-10-12 | 哈尔滨理工大学 | Cooling device of ultraviolet radiation meter probe |
| CN108844567A (en) * | 2018-04-19 | 2018-11-20 | 大连民族大学 | A kind of full tungsten is towards plasma sample stage |
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