CN115295176B - Tokamak divertor particle removal equipment - Google Patents
Tokamak divertor particle removal equipment Download PDFInfo
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- CN115295176B CN115295176B CN202210951177.4A CN202210951177A CN115295176B CN 115295176 B CN115295176 B CN 115295176B CN 202210951177 A CN202210951177 A CN 202210951177A CN 115295176 B CN115295176 B CN 115295176B
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- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/13—First wall; Blanket; Divertor
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/05—Thermonuclear fusion reactors with magnetic or electric plasma confinement
- G21B1/057—Tokamaks
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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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Abstract
The invention relates to the technical field of tokamak, and discloses a tokamak divertor particle removing device which is arranged in a neck tube of an upper window of a tokamak vacuum chamber and comprises a cold screen, a radiation baffle, a liquid nitrogen pipeline and a liquid helium pipeline, wherein the radiation baffle is arranged at the bottom end of the cold screen, a bottom plate is arranged at the upper end of the cold screen, the liquid nitrogen pipeline is arranged on the inner wall of the cold screen, the radiation baffle and the bottom plate are connected with the liquid nitrogen pipeline, and a low-temperature adsorption plate communicated with the liquid helium pipeline is arranged inside the cold screen. The method achieves the purpose of eliminating particles of the divertor, and simultaneously has lower sensitivity to temperature change compared with a low-temperature condensation method, can reduce the risk of particle analysis reflux, reduce disturbance to plasma, and ensure long-pulse discharge, thereby ensuring the effect of eliminating particles and ensuring that tokamak realizes high-parameter long-pulse plasma operation.
Description
Technical Field
The invention relates to the technical field of tokamak, in particular to a plug-in type tokamak divertor particle removal device based on low-temperature adsorption.
Background
Nuclear energy is becoming a new generation clean, sustainable energy source of increasing attention. The fusion energy occupies extremely high position in nuclear energy due to the characteristics of safety, rich fuel resources and the like. Tokamak is currently the most widely studied type of controllable nuclear fusion device, and is considered the most viable form of commercial fusion reactor in the future.
The vacuum chamber is one of the important components of tokamak, providing a high vacuum environment for fusion plasma operation. The divertor is a key component in the vacuum chamber, and has the main functions of collecting particle flow and heat flow from central plasma, reducing the influence of impurities on the central plasma and effectively improving discharge parameters; in order to avoid particle backflow in the divertor region, a divertor particle removal device (divertor gas extraction system) is designed and the particles collected by the divertor are effectively extracted to ensure steady state operation of the plasma.
The fuel for fusion reaction of the tolcard Ma Kezhong is isotope deuterium and tritium of hydrogen, and particles of the fuel are mainly removed by a molecular pump air suction system, a diffusion pump air suction system and a cryopump. However, molecular pump pumping systems have poor hydrogen pumping capacity, and diffusion pump pumping systems are prone to device contamination due to pump oil backflow. The low-temperature pump has wide application prospect in the field of partial filter particle elimination due to the characteristics of high pumping speed, high cleaning efficiency, flexible structure and the like of hydrogen.
Currently, there are two forms of cryopumps for divertor particle removal equipment, one is an external cryopump mounted outside the window of the vacuum chamber, such as ite; the other is a built-in annular cryopump installed inside the vacuum chamber (bottom of the divertor), such as EAST in China, JET in the United kingdom. The external cryogenic pump is connected with the divertor through the window neck tube, so that the conductance is lower, and the air extraction efficiency is lower. Although the built-in cryogenic pump is arranged near the divertor, the pumping efficiency is high, but the operation risk is high and the maintenance difficulty is extremely high. In addition, the partial filter cryopump of tokamak usually adopts a cryocondensation method to pump out gas particles. However, under a certain cold source condition, when the air pressure of the divertor is enhanced, the heat load of the low-temperature plate caused by heat convection, sensible heat and latent heat is increased, the temperature of the low-temperature pump is difficult to maintain, particles condensed on the surface of the low-temperature pump are easy to release, and the air extraction effect of the low-temperature pump is seriously affected.
Disclosure of Invention
In order to solve the technical problems, the invention provides a tokamak divertor particle removal device, which ensures the particle removal effect and ensures the tokamak to realize high-parameter long-pulse plasma operation.
The technical scheme adopted for solving the technical problems is as follows:
the utility model provides a tokamak divertor particle removal equipment installs in the window neck pipe on the tokamak vacuum chamber, including cold shield, liquid nitrogen pipeline, liquid helium pipeline, the bottom of cold shield is equipped with radiation baffle, the upper end of cold shield is equipped with the bottom plate, the liquid nitrogen pipeline sets up the inner wall of cold shield, just radiation baffle reaches the bottom plate all with the liquid nitrogen pipeline is connected, the inside of cold shield be equipped with the low temperature adsorption plate that liquid helium pipeline is linked together.
Preferably, the low-temperature adsorption plate comprises a plurality of low-temperature adsorption plate bodies, active carbon is arranged on two sides of each low-temperature adsorption plate body, and through holes communicated with the liquid helium pipeline are formed in the low-temperature adsorption plate bodies along the length direction of each low-temperature adsorption plate body.
Preferably, the liquid helium pipeline comprises a liquid helium outlet pipeline penetrating through the bottom plate, a liquid helium inlet pipeline is coaxially inserted in the liquid helium outlet pipeline, and the plurality of low-temperature adsorption plate main bodies are respectively communicated with the liquid helium inlet pipeline and the liquid helium outlet pipeline.
Preferably, the low-temperature adsorption plate body is connected with the liquid helium pipeline through a transition joint, one part of the low-temperature adsorption plate body is connected with the liquid helium pipeline in parallel, and the other part of the low-temperature adsorption plate body is connected with the liquid helium pipeline in series.
Preferably, a flow channel communicated with the liquid nitrogen pipeline is arranged on the bottom plate, and a cover plate is covered on the flow channel.
Preferably, the liquid nitrogen pipeline comprises a pipeline main body penetrating through the radiation baffle plate and being attached to the inner wall of the cold screen, a liquid nitrogen inlet pipeline and a liquid nitrogen outlet pipeline communicated with the flow channel, and two ends of the pipeline main body are respectively connected with the liquid nitrogen inlet pipeline and the flow channel.
Preferably, the radiation baffle comprises a plurality of radiation baffle bodies which are sequentially arranged at intervals, wherein the cross section of the radiation baffle body is V-shaped, or the radiation baffle bodies are arranged in a shutter type.
Preferably, the distance a between adjacent V-shaped radiation baffle bodies is 10-20 mm, the included angle theta between the radiation baffle bodies is 110-130 degrees, and the height h of the radiation plate is 30-50 mm; the distance a between adjacent shutter type radiation baffle bodies is 15-25 mm, the included angle theta between the radiation baffle bodies is 50-70 degrees, and the height h of the radiation plate is 30-50 mm. .
Preferably, the outer wall of the cold screen is wound with a heating wire, and a cold screen temperature sensor is arranged on the outer wall of the cold screen.
A tokamak device comprising a first wall, a vacuum chamber, a divertor and a vacuum chamber upper window neck connected, a cover flange arranged at the upper end of the vacuum chamber upper window neck, a divertor particle removing device as set forth in any one of claims 1-9, a support flange arranged in the vacuum chamber upper window neck, the support flange connected with the cover flange through a positioning support tube, and a bottom plate connected with the support flange through gravity support.
Compared with the prior art, the tokamak divertor particle removal equipment provided by the embodiment of the invention has the beneficial effects that: the purpose of removing the particles of the divertor is achieved by arranging the low-temperature adsorption plate to adsorb the gas particles, and simultaneously, the pumping speed and pumping capacity of the divertor can be improved by increasing the flow rate of liquid helium and reducing the temperature of the liquid helium inlet by arranging the liquid helium pipeline to connect the low-temperature adsorption plate; compared with a low-temperature condensation method, the method has lower sensitivity to temperature change, can reduce the risk of particle analysis reflux, reduce disturbance to plasma, ensure long-pulse discharge, further ensure the particle removal effect and ensure that tokamak realizes high-parameter long-pulse plasma operation. The invention has simple structure, good use effect and easy popularization and use.
Drawings
Fig. 1 is a schematic structural view of a tokamak device of the present invention.
Fig. 2 is a partial enlarged view of fig. 1.
FIG. 3 is a schematic structural view of a divertor particle excluding apparatus of the present invention.
FIG. 4 is a cross-sectional view of a divertor particle removal device of the present invention.
FIG. 5 is a schematic diagram of the structure of the cryogenic adsorption plate and liquid helium line of the present invention.
Fig. 6 is a schematic diagram of the structure of the liquid nitrogen pipeline of the present invention.
FIG. 7 is a schematic view of the structure of the bottom plate and the liquid nitrogen channel cover plate of the present invention.
Fig. 8 is a schematic structural view of a radiation shield of the present invention.
Wherein: 1-first wall, 2-divertor, 3-vacuum chamber upper window neck, 4-cover flange, 5-vacuum bellows, 6-support flange, 7-divertor particle removal equipment, 8-vacuum chamber, 9-cold screen sleeve, 10-positioning support cylinder, 11-cold screen, 12-heating wire, 13-liquid nitrogen inlet conduit, 14-liquid helium conduit, 15-liquid nitrogen outlet conduit, 16-gravity support, 17-liquid nitrogen conduit, 18-liquid helium inlet conduit, 19-liquid helium outlet conduit, 20-liquid helium conduit temperature sensor, 21-bottom plate, 22-cover plate, 23-flow channel, 24-cold screen temperature sensor, 25-cryogenic adsorption plate, 26-transition joint, 27-cryogenic adsorption plate temperature sensor, 28-radiation shield.
Detailed Description
The following describes in further detail the embodiments of the present invention with reference to the drawings and examples. The following examples are illustrative of the invention and are not intended to limit the scope of the invention.
As shown in fig. 1, the invention discloses a tokamak device, which comprises a first wall 1, a vacuum chamber 8, a divertor 2 and a vacuum chamber upper window neck 3 which are connected, wherein the upper end of the vacuum chamber upper window neck 3 is provided with a cover plate flange 4, the device further comprises a divertor particle removing device 7, the inside of the vacuum chamber upper window neck 3 is provided with a support flange 6, the support flange 6 is connected with the cover plate flange 4 through a positioning support cylinder 10, the divertor particle removing device 7 is arranged in the tokamak vacuum chamber upper window neck 3 and comprises a cold screen 11, a liquid nitrogen pipeline 17 and a liquid helium pipeline 14, the bottom end of the cold screen 11 is provided with a radiation baffle 28, the upper end of the cold screen 11 is provided with a bottom plate 21, the liquid nitrogen pipeline 17 is arranged on the inner wall of the cold screen 11, the radiation baffle 28 and the bottom plate 21 are both connected with the liquid nitrogen pipeline 17, and the inside of the cold screen 11 is provided with a low-temperature adsorption plate 25 communicated with the liquid helium pipeline 17. The bottom plate 21 is connected to the support flange 6 by means of a gravitational support 16. Specifically, the suction inlet end of the divertor particle removal device 7 faces the divertor 2 and is mounted to the divertor 2 along the axis of the window neck 3 on the tokamak vacuum chamber.
Specifically, the cold screen 11 and the bottom plate 21 can prevent the low-temperature adsorption plate 25 from being subjected to heat radiation by the vacuum chamber 8 and the divertor support structure;
the radiation shield 28 has a gas conductance as large as possible and serves as a heat radiation shield for the low-temperature adsorption plate 25. The radiation baffle plate 28 can also pre-cool the pumped air body, so that the heat load on the low-temperature adsorption plate 25 is reduced;
the function of the low-temperature adsorption plate 25 is to adsorb gas particles, so as to achieve the purpose of removing the divertor particles;
the liquid nitrogen pipeline 17 is used for connecting and cooling the radiation baffle 28, the cold shield 11 and the bottom plate 21 and is used as a flow channel of liquid nitrogen;
the liquid helium line 18 is used to connect the low-temperature adsorption plate 25 and serves as a flow passage for liquid helium.
The tokamak divertor particle removing equipment based on the technical characteristics achieves the purpose of removing the divertor particles by arranging the low-temperature adsorption plate 25 to adsorb the gas particles, and simultaneously increases the pumping speed and pumping capacity by increasing the flow rate of liquid helium and reducing the temperature of the liquid helium inlet by arranging the liquid helium pipeline 14 to be connected with the low-temperature adsorption plate 25; compared with a low-temperature condensation method, the method has lower sensitivity to temperature change, can reduce the risk of particle analysis reflux, reduce disturbance to plasma, ensure long-pulse discharge, further ensure the particle removal effect and ensure that tokamak realizes high-parameter long-pulse plasma operation. The invention has simple structure, good use effect and easy popularization and use.
The outline structure of the divertor particle removing device 7 can be adjusted and designed according to the outline of the window neck tube on the vacuum chamber, so that the space environment of the window neck tube can be effectively utilized, and the air extraction rate of the divertor particle removing device can be improved. As shown in fig. 3 and 4, the cold shield 11 has the same shape as the window neck 3 on the vacuum chamber to use space as much as possible, and the specific size of the cold shield 11 needs to be determined in combination with the actual requirement, and the actual size of the cold shield 11 of this example is determined in consideration of the arrangement space of the cryogenic adsorption plate 25, the liquid helium pipeline 14 and the liquid nitrogen pipeline 17.
The outer wall surface of the cold screen 11 is provided with a cold screen temperature sensor 24 for detecting the temperature of the cold screen 11 in the heating regeneration stage and the working stage of the particle removal equipment. As shown in fig. 3, 4, 6 and 7, the bottom plate 21 is designed with two circular through holes for arranging the liquid helium line 14. The bottom plate 21 is grooved as a bottom plate liquid nitrogen flow passage 23, and the bottom plate liquid nitrogen passage cover plate 22 having the same shape as the passage is welded with the bottom plate 21 to complete the sealing. The bottom plate 21 is designed with 7 liquid nitrogen inlets and 1 liquid nitrogen outlet; a gap with a width of 1mm and a height of 2mm is cut along the boundary of the bottom plate 21 so as to be welded with the cold screen 11, and 7 notches are designed at the boundary of the bottom plate 21 for arranging the liquid nitrogen pipeline 17.
As shown in fig. 4 and 8, the radiation shield 28 includes a plurality of radiation shield bodies arranged in a sequential and spaced manner, the cross section of the radiation shield body is V-shaped, or the plurality of radiation shield bodies are arranged in a louver type manner. The shutter type baffle is used for scenes with high requirements on pumping speed and small external radiant heat; the V-shaped baffles are generally used in situations where the external environment radiates a relatively large amount of heat and the pumping speed is not required. The radiation baffle plate bodies can be adjusted according to actual demands when being specifically arranged, specifically, the value range of the interval a between the adjacent V-shaped radiation baffle plate bodies is 10-20 mm, the value range of the included angle theta of the radiation baffle plate bodies is 110-130 degrees, and the value range of the height h of the radiation plate is 30-50 mm; the distance a between adjacent shutter type radiation baffle bodies is 15-25 mm, the included angle theta between the radiation baffle bodies is 50-70 degrees, and the height h of the radiation plate is 30-50 mm. In the present invention, preferably, if V-shaped baffles are adopted, the distance a between adjacent radiation baffle bodies is 15mm, the radiation baffle included angle θ is 120 °, and the height h is 40mm; if the shutter type baffle plates are taken, the distance a between the adjacent radiation baffle plates is 20mm, the inclination angle theta of the plate is 60 degrees, and the height h is 40mm.
In particular to this example, since the divertor particle excluding device 7 faces the high temperature surface of the divertor 2, the external radiant heat is large, and the pumping speed can be increased by increasing the flow rate of liquid helium, a V-shaped baffle is employed. The middle opening of each radiation shield is connected to a liquid nitrogen line 17, which liquid nitrogen line 17 cools the radiation shield 28 by heat conduction. The radiation shield 28 is made of pure copper, and the surface is blackened to absorb external heat radiation as much as possible, and to prevent excessive radiant heat from being reflected to the low-temperature adsorption plate 25. The arrangement mode, the shape structure, the size and the number of the low-temperature adsorption plates can be flexibly adjusted according to the window neck tube space and the working requirement on different Tokamak vacuum chambers.
As shown in fig. 4 and 5, the low-temperature adsorption plate 25 includes a plurality of low-temperature adsorption plate bodies, and both side surfaces of the low-temperature adsorption plate bodies are adhered with coconut shell activated carbon for adsorbing gas particles, and specifically, inorganic glue is adhered, and compared with rubber, the inorganic glue is radiation-resistant, and is applicable to fusion neutron and gamma radiation environments, so that the service life of the particle removing device is effectively prolonged. The low-temperature adsorption plate body is provided with a through hole communicated with the liquid helium pipeline 18 along the length direction. According to the practical requirements, in order to increase the adsorption area as much as possible in a narrow space of the cold screen 11 and realize the maximization of space utilization, the whole low-temperature adsorption plates 25 are symmetrically distributed, the low-temperature adsorption plate bodies and the wall surface of the cold screen 11 are arranged at a certain angle, and the low-temperature adsorption plates 25 are formed by 21 cuboid low-temperature adsorption plate bodies with 2 sizes. Wherein the total of 19 small low-temperature adsorption plate bodies is 450mm in length and 50mm in width, and the total of 2 large low-temperature adsorption plate bodies is 450mm in length and 110mm in width.
In this embodiment, four low-temperature adsorption plate temperature sensors 27 are disposed on the low-temperature adsorption plate body to detect the temperature change thereof, and when the low-temperature adsorption plate temperature sensors 27 show that the low-temperature adsorption plate temperature rise exceeds 2K, the flow rate of liquid helium is increased to reduce the temperature of the low-temperature adsorption plate according to the actual situation. The low-temperature adsorption plate body is provided with through holes along the length direction for connecting the liquid helium pipeline 14, and the through holes form cooling channels for liquid helium to flow, and the cooling channels are designed and optimized according to the temperature distribution simulation research of the low-temperature adsorption plate 25. The cryogenic adsorption plate is connected to the liquid helium line 14 by a transition joint 26.
As shown in fig. 4 and 5, the liquid helium pipeline 14 includes a liquid helium outlet pipe 19 penetrating through the bottom plate 21, a liquid helium inlet pipe 18 is coaxially inserted into the liquid helium outlet pipe 19, and a plurality of low-temperature adsorption plate bodies are respectively communicated with the liquid helium inlet pipe 18 and the liquid helium outlet pipe 19. Namely, the liquid helium inlet pipeline 18 and the liquid helium outlet pipeline 19 of the liquid helium pipeline 14 are of a double-layer concentric tube structure, the inner layer pipeline of the concentric tube is the liquid helium inlet pipeline 18 of the liquid helium pipeline 14, and the outer layer annular pipeline is the liquid helium outlet pipeline 19 of the liquid helium pipeline 14. The double-layer concentric tube structure has the advantages that: the outer annular outlet pipe can play a role in heat insulation protection on the inner inlet pipe. The liquid helium inlet pipeline 18 and the liquid helium outlet pipeline 19 are divided into different branches and connected with a low-temperature adsorption plate 25, wherein one part of the low-temperature adsorption plate body is connected with the liquid helium pipeline 14 in parallel, and the other part of the low-temperature adsorption plate body is connected with the liquid helium pipeline 14 in series. Namely, the series connection and the parallel connection between the low-temperature adsorption plate bodies are combined. The advantage is that if all the low-temperature adsorption plates 25 with the rear series route have higher temperature, all the parallel connection can reduce the flow of liquid helium in each low-temperature adsorption plate 25, which is also unfavorable for cooling the low-temperature adsorption plates; the series-parallel connection mode is designed and optimized through temperature distribution analysis and overall pressure drop analysis of the low-temperature adsorption plate 25; the inlet and outlet of the liquid helium pipeline 14 are double-layer concentric pipes, the inner layer pipeline of the concentric pipes is an inlet pipeline 18 of liquid helium, the outer layer annular pipeline is an outlet pipeline 19 of liquid helium, and the outlet pipeline plays a role in heat insulation protection on the inlet pipeline; the liquid helium pipeline is made of 316L stainless steel.
The inlet and outlet pipes of the liquid helium pipeline 14 are respectively provided with a low-temperature sensor for detecting temperature change. As shown in fig. 4 and 6, the liquid nitrogen pipeline 17 shares a liquid nitrogen inlet pipeline 13 and a liquid nitrogen outlet pipeline 15, and the liquid nitrogen inlet pipeline 13 and the liquid nitrogen outlet pipeline 15 are connected by different branches and cool the bottom plate 21, the cold shield 11 and the radiation baffle 28. Specifically, the liquid nitrogen pipeline 17 comprises a pipeline main body penetrating through the radiation baffle 28 and being attached to the inner wall of the cold screen 11, a liquid nitrogen inlet pipeline 13 and a liquid nitrogen outlet pipeline 15 communicated with the flow channel, and two ends of the pipeline main body are respectively connected with the liquid nitrogen inlet pipeline 13 and the flow channel 23.
Fig. 2 shows an enlarged partial view of the support part of the divertor particle excluding device 7. The divertor particle removal device 7 is connected to the support flange 6 by three gravity supports 16, the connection being by bolts; the support flange 6 is connected with the upper window neck pipe cover plate flange 4 of the vacuum chamber through a positioning support cylinder 10 in a vacuum brazing mode. Three through holes are formed in the flange 4 of the upper window neck pipe cover plate of the vacuum chamber and are respectively used for penetrating a double-layer concentric pipeline of the liquid helium pipeline 14, the liquid nitrogen inlet pipeline 13 and the liquid nitrogen outlet pipeline 15. In order to seal the gap between the through hole and the pipeline, a vacuum bellows 5 is adopted to be welded with a window neck pipe cover plate flange 4 and the pipeline on the vacuum chamber respectively. The vacuum corrugated pipe sealing mode can absorb the thermal strain of the double-layer concentric pipe caused by the temperature cyclic change, reduces the cyclic thermal stress of the double-layer concentric pipe, and effectively improves the fatigue life of the liquid helium pipeline 14. The portion of the double concentric tube exposed to the tokamak vacuum chamber environment is surrounded by a cold screen sleeve 9 to avoid the double concentric tube from being radiated by heat from the vacuum chamber upper window neck 3 and the vacuum chamber upper window neck cover flange 4. The cold shield sleeve 9 is welded to the liquid nitrogen inlet pipe 13 and the liquid nitrogen outlet pipe 15, and is cooled by heat conduction.
The working flow of the tokamak divertor particle removal device of the present invention is as follows:
and in the beginning stage of air extraction, the divertor particle removing equipment is cooled by external refrigeration equipment, and the temperature change can be monitored by a temperature sensor in the cooling stage. After the preset temperature is reached, the divertor particle removing equipment works normally (air extraction), and in the working stage, the temperature of the low-temperature adsorption plate 25 is monitored by a temperature sensor, and when the temperature rise of the low-temperature adsorption plate 25 exceeds 2K, the liquid helium flow of an external cold source is required to be increased, so that the stability of the air extraction performance of the divertor particle removing equipment is ensured. When the pumping speed is lowered to 50% of normal value, the divertor particle removal equipment needs to be regenerated to resolve and discharge the gas particles on the low-temperature adsorption plate 25. Regeneration is divided into two ways: and regenerating after normal operation and accident conditions. In the normal operation regeneration process, the liquid nitrogen pipeline 17 keeps liquid nitrogen flowing, liquid helium in the liquid helium pipeline is discharged, the temperature of the low-temperature adsorption plate 25 is gradually increased to about 80K under the heat radiation effect of the cold screen 11, and helium gas and hydrogen isotope gas adsorbed by the low-temperature adsorption plate are analyzed. Regeneration after an accident condition refers to regeneration of the divertor particle removal device after cooling water leakage or atmospheric exposure occurs inside the tokamak vacuum chamber 5, and under the accident condition, activated carbon on the low-temperature adsorption plate 25 is easy to absorb water and poison, so that deep regeneration is required. In the deep regeneration process, liquid nitrogen and liquid helium are required to be discharged simultaneously, the cold screen 11 is heated to about 500K by the electric heating wire 12, and the temperature of the low-temperature adsorption plate 25 is raised by heat radiation of the cold screen 11. After the regeneration phase is completed, the temperature reduction process is repeated, and the divertor particle removal equipment can be put into operation again. When the divertor particle removing equipment needs maintenance, the bolts of the upper window neck pipe cover plate flange 4 of the vacuum chamber are removed, and the upper window neck pipe cover plate flange 4 and the divertor particle removing equipment 7 are lifted out by crane.
Compared with the prior art, the invention has the advantages that:
1. the insert type tokamak divertor particle removal equipment based on low-temperature adsorption has the advantages that the installation and the disassembly processes are simple and independent, the maintenance is convenient, and other interior parts of the tokamak vacuum chamber do not need to be dismantled;
2. the insert type tokamak divertor particle removing equipment based on low-temperature adsorption adopts liquid helium for circulating cooling, has high refrigerating capacity, and can improve the pumping speed and pumping capacity by increasing the flow rate of the liquid helium and reducing the temperature of a liquid helium inlet;
3. the insert type tokamak divertor particle removal equipment based on low-temperature adsorption adopts a low-temperature adsorption air extraction method, has lower sensitivity to temperature change compared with a low-temperature condensation method, can reduce the risk of particle analysis reflux, reduces disturbance to plasma, and ensures long-pulse discharge;
4. the adsorbent of the plug-in type tokamak divertor particle removal equipment based on low-temperature adsorption is bonded by adopting inorganic glue, and compared with rubber, the inorganic glue is radiation-resistant, so that the plug-in type tokamak divertor particle removal equipment based on low-temperature adsorption is applicable to fusion neutron and gamma radiation environments, and the service life of the particle removal equipment is effectively prolonged;
5. the insert type tokamak divertor particle removal equipment based on low-temperature adsorption does not comprise a moving part, has the advantage of magnetism resistance, and can stably work in a tokamak strong magnetic field environment.
The foregoing is merely a preferred embodiment of the present invention, and it should be noted that modifications and substitutions can be made by those skilled in the art without departing from the technical principles of the present invention, and these modifications and substitutions should also be considered as being within the scope of the present invention.
Claims (9)
1. The utility model provides a tokamak divertor particle removal equipment, installs in the window neck pipe on the tokamak vacuum chamber, its characterized in that: the liquid nitrogen pipeline is arranged on the inner wall of the cold shield, the radiation baffle plate and the bottom plate are connected with the liquid nitrogen pipeline, and a low-temperature adsorption plate communicated with the liquid helium pipeline is arranged in the cold shield.
2. A tokamak divertor particle removal device as in claim 1, wherein: the low-temperature adsorption plate comprises a plurality of low-temperature adsorption plate bodies, active carbon is arranged on two sides of each low-temperature adsorption plate body, and through holes communicated with the liquid helium pipeline are formed in the low-temperature adsorption plate bodies along the length direction of each low-temperature adsorption plate body.
3. A tokamak divertor particle removal device as in claim 2, wherein: the liquid helium pipeline comprises a liquid helium outlet pipeline penetrating through the bottom plate, a liquid helium inlet pipeline is coaxially inserted in the liquid helium outlet pipeline, and the low-temperature adsorption plate main bodies are respectively communicated with the liquid helium inlet pipeline and the liquid helium outlet pipeline.
4. A tokamak divertor particle removal device as in claim 2, wherein: the low-temperature adsorption plate main body is connected with the liquid helium pipeline through a transition joint, one part of the low-temperature adsorption plate main body is connected with the liquid helium pipeline in parallel, and the other part of the low-temperature adsorption plate main body is connected with the liquid helium pipeline in series.
5. A tokamak divertor particle removal device as in claim 1, wherein: the bottom plate is provided with a flow channel communicated with the liquid nitrogen pipeline, and the flow channel is covered with a cover plate.
6. A tokamak divertor particle removal device as in claim 5, wherein: the liquid nitrogen pipeline comprises a pipeline main body penetrating through the radiation baffle plate and being attached to the inner wall of the cold screen, a liquid nitrogen inlet pipeline and a liquid nitrogen outlet pipeline communicated with the flow channel, and two ends of the pipeline main body are respectively connected with the liquid nitrogen inlet pipeline and the flow channel.
7. A tokamak divertor particle removal device as in claim 1, wherein: the radiation baffle comprises a plurality of radiation baffle bodies which are sequentially arranged at intervals, wherein the cross section of the radiation baffle body is V-shaped, or the radiation baffle bodies are arranged in a shutter type.
8. A tokamak divertor particle removal device as in claim 7, wherein: the value range of the interval a between the adjacent V-shaped radiation baffle bodies is 10-20 mm, the value range of the included angle theta of the radiation baffle bodies is 110-130 degrees, and the value range of the height h of the radiation plate is 30-50 mm; the distance a between adjacent shutter type radiation baffle bodies is 15-25 mm, the included angle theta between the radiation baffle bodies is 50-70 degrees, and the height h of the radiation plate is 30-50 mm.
9. A tokamak divertor particle removal device as in claim 1, wherein: the outer wall winding of cold shield has the heater strip, the outer wall of cold shield is equipped with cold shield temperature sensor.
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| CN110985339A (en) * | 2019-11-25 | 2020-04-10 | 中国工程物理研究院材料研究所 | Column built-in cryogenic pump |
| CN112096597A (en) * | 2020-09-16 | 2020-12-18 | 中国科学技术大学 | Cryogenic pump with double-valve structure |
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2022
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| CN115295176A (en) | 2022-11-04 |
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