CN115295176A - Tokamak divertor particle removing equipment - Google Patents

Tokamak divertor particle removing equipment Download PDF

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Publication number
CN115295176A
CN115295176A CN202210951177.4A CN202210951177A CN115295176A CN 115295176 A CN115295176 A CN 115295176A CN 202210951177 A CN202210951177 A CN 202210951177A CN 115295176 A CN115295176 A CN 115295176A
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pipeline
liquid helium
divertor
tokamak
liquid nitrogen
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CN115295176B (en
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陈肇玺
杨庆喜
宋云涛
彭学兵
张航
张程鹏
于志航
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Hefei Institutes of Physical Science of CAS
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Hefei Institutes of Physical Science of CAS
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/11Details
    • G21B1/13First wall; Blanket; Divertor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21BFUSION REACTORS
    • G21B1/00Thermonuclear fusion reactors
    • G21B1/05Thermonuclear fusion reactors with magnetic or electric plasma confinement
    • G21B1/057Tokamaks
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)

Abstract

The invention relates to the technical field of tokamak, and discloses a particle removing device for a tokamak divertor, which is arranged in a neck pipe 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 bottom end of the cold screen is provided with the radiation baffle, the upper end of the cold screen is provided with a bottom plate, the liquid nitrogen pipeline is arranged on the inner wall of the cold screen, the radiation baffle and the bottom plate are both connected with the liquid nitrogen pipeline, and a low-temperature adsorption plate communicated with the liquid helium pipeline is arranged inside the cold screen. Compared with a low-temperature condensation method, the method has the advantages that the purpose of removing the divertor particles is achieved, the sensitivity degree of the divertor particles to temperature change is lower, the risk of particle analysis backflow is reduced, the disturbance to the plasma is reduced, and the long-pulse discharge is ensured, so that the removal effect of the particles is ensured, and the Tokamak is ensured to realize the operation of the high-parameter long-pulse plasma.

Description

Tokamak divertor particle removing equipment
Technical Field
The invention relates to the technical field of tokamak, in particular to plug-in tokamak divertor particle removing equipment based on low-temperature adsorption.
Background
Nuclear energy is receiving more and more attention as a new generation of clean and sustainable energy. The fusion energy occupies a very 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 internationally, and is considered the most feasible form of future commercial fusion reactor.
The vacuum chamber is one of the important parts of the Tokamak and provides a high vacuum environment for the operation of fusion plasma. The divertor is a key component in the vacuum chamber, and has the main functions of collecting particle flow and heat flow from the central plasma, reducing the influence of impurities on the central plasma and effectively improving discharge parameters; in order to avoid the backflow of particles in the divertor region, a divertor particle removal device (a divertor gas extraction system) needs to be designed to timely and effectively extract the particles collected by the divertor so as to ensure the steady-state operation of the plasma.
The fuel for fusion reaction in tokamak is hydrogen isotope deuterium and tritium, and the particle elimination mainly comprises a molecular pump air pumping system, a diffusion pump air pumping system and a low-temperature pump. However, the molecular pump pumping system has a weak capacity for pumping hydrogen, and the diffusion pump pumping system is prone to device contamination caused by backflow of pump oil. The cryopump has the characteristics of high pumping speed, high cleaning efficiency, flexible structure and the like on hydrogen, so the cryopump has wide application prospect in the field of divertor particle removal.
Currently, there are two forms of cryopumps used in divertor particle removal equipment, one being an external cryopump mounted outside the vacuum chamber window, such as ITER; the other is a built-in ring cryopump installed inside the vacuum chamber (bottom of divertor), such as EAST in china, JET in uk. The external cryogenic pump is connected with the divertor through the window neck tube, and the conductance is lower, and the pumping efficiency is also 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 very high. In addition, the divertor cryopump of tokamak mostly adopts a method of low-temperature condensation to pump out gas particles. However, under the condition of a certain cooling source, when the air pressure of the divertor is increased, the heat load of the cryopanel caused by heat convection, sensible heat and latent heat is increased, the temperature of the cryopump is difficult to maintain, particles condensed on the surface of the cryopump are easy to release, and the air pumping effect of the cryopump is seriously influenced.
Disclosure of Invention
In order to solve the technical problems, the invention provides a particle removing device for a tokamak divertor, which ensures the particle removing effect and ensures the tokamak to realize the high-parameter long-pulse plasma operation.
The technical scheme adopted by the invention for solving the technical problem is as follows:
the utility model provides a support kamak divertor particle gets rid of equipment, installs in the real empty room upper window neck pipe of support kamak, 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 the liquid helium pipeline is linked together.
Preferably, the low temperature adsorption plate comprises a plurality of low temperature adsorption plate main bodies, activated carbon is arranged on two sides of each low temperature adsorption plate main body, and through holes communicated with the liquid helium pipeline are formed in the low temperature adsorption plate main bodies along the length directions of the low temperature adsorption plate main bodies.
Preferably, the liquid helium pipeline comprises a liquid helium outlet pipeline penetrating through the bottom plate, a liquid helium inlet pipeline is coaxially inserted into 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 main body is connected with the liquid helium pipeline through a transition joint, and 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.
Preferably, the bottom plate is provided with a flow channel communicated with the liquid nitrogen pipeline, and the flow channel is covered by a cover plate.
Preferably, the liquid nitrogen pipeline comprises a pipeline main body penetrating through the radiation baffle and attached to the inner wall of the cold shield, 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 main bodies which are sequentially arranged at intervals, the cross section of each radiation baffle main body is V-shaped, or the plurality of radiation baffle main bodies are arranged in a shutter type.
Preferably, the distance a between the adjacent V-shaped radiation baffle main bodies ranges from 10mm to 20mm, the included angle theta of the radiation baffle main bodies ranges from 110 degrees to 130 degrees, and the height h of the radiation plate ranges from 30 mm to 50 mm; the distance a between adjacent louver type radiation baffle main bodies ranges from 15mm to 25 mm, the included angle theta of the radiation baffle main bodies ranges from 50 degrees to 70 degrees, and the height h of the radiation plates ranges from 30 mm to 50 mm. .
Preferably, the outer wall of the cold screen is wound with a heating wire, and the outer wall of the cold screen is provided with a cold screen temperature sensor.
A tokamak device, comprising a first wall, a vacuum chamber, a divertor and an upper window neck of the vacuum chamber which are connected, wherein the upper end of the upper window neck of the vacuum chamber is provided with a cover plate flange, and the divertor particle removing apparatus of any one of claims 1 to 9, wherein a support flange is arranged inside the upper window neck of the vacuum chamber, the support flange is connected with the cover plate flange through a positioning support cylinder, and a bottom plate is connected with the support flange through gravity support.
Compared with the prior art, the particle removing equipment for the tokamak divertor of the embodiment of the invention has the following beneficial effects: the purpose of removing the particles of the divertor is achieved by arranging the low-temperature adsorption plate to adsorb the gas particles, and meanwhile, the pumping speed and the pumping capacity of the divertor can be improved by increasing the flow rate of the liquid helium and reducing the temperature of the liquid helium inlet by arranging the liquid helium pipeline to be connected with 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 backflow, reduce the disturbance to the plasma, and ensure long-pulse discharge, thereby ensuring the particle removal effect and ensuring the achievement of high-parameter long-pulse plasma operation by Tokamak. The invention has simple structure, good use effect and easy popularization and use.
Drawings
Fig. 1 is a schematic structural view of the tokamak apparatus of the present invention.
Fig. 2 is a partially enlarged view of fig. 1.
FIG. 3 is a schematic view showing the structure of the divertor particle elimination apparatus of the present invention.
Fig. 4 is a cross-sectional view of a divertor particle exclusion apparatus of the present invention.
FIG. 5 is a schematic diagram of the low temperature adsorption plate and the liquid helium pipeline according to the present invention.
FIG. 6 is a schematic diagram of the liquid nitrogen line of the present invention.
FIG. 7 is a schematic structural diagram of a bottom plate and a liquid nitrogen channel cover plate of the present invention.
Fig. 8 is a schematic view of the structure 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 exclusion apparatus, 8-vacuum chamber, 9-cold shield sleeve, 10-positioning support cylinder, 11-cold shield, 12-heater wire, 13-liquid nitrogen inlet pipe, 14-liquid helium pipe, 15-liquid nitrogen outlet pipe, 16-gravity support, 17-liquid nitrogen pipe, 18-liquid helium inlet pipe, 19-liquid helium outlet pipe, 20-liquid helium pipe temperature sensor, 21-bottom plate, 22-cover plate, 23-flow channel, 24-cold shield temperature sensor, 25-low temperature adsorption plate, 26-transition joint, 27-low temperature adsorption plate temperature sensor, 28-radiation baffle.
Detailed Description
The following detailed description of embodiments of the present invention is provided in connection with the accompanying drawings and examples. The following examples are intended to illustrate the invention but are not intended to limit the scope of the invention.
As shown in fig. 1, the present invention discloses a tokamak apparatus, which comprises a first wall 1, a vacuum chamber 8, a divertor 2, a vacuum chamber upper window neck 3, a divertor particle removal device 7, wherein the first wall 1, the vacuum chamber 8, the divertor 2, the vacuum chamber upper window neck 3 and the divertor particle removal device 7 are connected, a support flange 6 is arranged inside the vacuum chamber upper window neck 3, the support flange 6 is connected with the cover flange 4 through a positioning support cylinder 10, the divertor particle removal device 7 is arranged inside 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, a radiation baffle 28 is arranged at the bottom end of the cold screen 11, a bottom plate 21 is arranged at the upper end of the cold screen 11, 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 a low temperature adsorption plate 25 communicated with the liquid helium pipeline 17 is arranged inside the cold screen 11. The base plate 21 is connected to the support flange 6 by means of a gravity support 16. Specifically, the divertor particle elimination apparatus 7 has an exhaust inlet end facing the divertor 2 and is attached to the divertor 2 along the axial direction of the window neck 3 on the tokamak vacuum chamber.
In particular, the cold shield 11 and the bottom plate 21 can prevent the low temperature adsorption plate 25 from being thermally radiated by the vacuum chamber 5 and the divertor support structure;
the radiation shield 28 has as large a gas conductance as possible and serves as a thermal radiation shield for the cryogenic absorption plate 25. The radiation shield 28 may also pre-cool the pumped gas, reducing the thermal load on the cryoadsorption plate 25;
the low-temperature adsorption plate 25 has the function of adsorbing gas particles, so that the aim of removing the particles of the divertor is fulfilled;
the liquid nitrogen pipeline 17 is used for connecting and cooling the radiation baffle 28, the cold screen 11 and the bottom plate 21 and is used as a flow channel of liquid nitrogen;
the liquid helium pipeline 18 is used for connecting the low-temperature adsorption plate 25 and is used as a flow channel of liquid helium.
The particle removing equipment of the Tokamak divertor based on the technical characteristics achieves the aim of removing particles of the divertor by arranging the low-temperature adsorption plate 25 to adsorb gas particles, and simultaneously improves the pumping speed and the pumping capacity of the particle removing equipment by increasing the flow rate of liquid helium and reducing the temperature of a liquid helium inlet by arranging the liquid helium pipeline 18 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 backflow, reduce the disturbance to the plasma, and ensure long-pulse discharge, thereby ensuring the particle removal effect and ensuring the achievement of high-parameter long-pulse plasma operation by Tokamak. The invention has simple structure, good use effect and easy popularization and use.
The shape structure of the divertor particle removal apparatus 7 can be adjusted and designed according to the shape of the window neck on the vacuum chamber, so that the space environment of the window neck can be effectively utilized, and the air extraction rate can be increased. As shown in fig. 3 and 4, the shape of the cold shield 11 is the same as the shape of the window neck 3 on the vacuum chamber to use space as much as possible, the specific size of the cold shield 11 is determined by combining practical requirements, and the practical size of the cold shield 11 in this example is determined by considering the arrangement space of the low-temperature adsorption plate 25, the liquid helium pipeline 14 and the liquid nitrogen pipeline 17.
The outer wall surface of the cold screen 11 is distributed 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 pipeline 14. The bottom plate 21 is grooved to serve as a bottom plate liquid nitrogen flow channel 23, and a bottom plate liquid nitrogen channel cover plate 22 with the same shape as the channel is welded with the bottom plate 21 to complete sealing. The bottom plate 21 is designed with 7 liquid nitrogen inlets and 1 liquid nitrogen outlet; a gap with the width of 1mm and the height of 2mm is cut along the boundary of the bottom plate 21 so as to be welded with the cold shield 11, and 7 gaps are designed at the boundary of the bottom plate 21 and used for arranging the liquid nitrogen pipeline 17.
As shown in fig. 4 and 8, the radiation baffle 28 includes a plurality of radiation baffle bodies arranged in sequence at intervals, and the cross section of the radiation baffle body is V-shaped, or the plurality of radiation baffle bodies are arranged in a louver type. The shutter type baffle is used for scenes with high pumping speed requirement and small external radiant heat; the V-shaped baffle is generally used for the conditions that the radiation heat of the external environment is large and the pumping speed requirement is not high. The radiation baffle plate main bodies can be adjusted according to actual requirements when being specifically arranged, specifically, the range of the distance a between the adjacent V-shaped radiation baffle plate main bodies is 10-20 mm, the range of the included angle theta of the radiation baffle plate main bodies is 110-130 degrees, and the range of the height h of the radiation plate is 30-50 mm; the distance a between adjacent shutter type radiation baffle main bodies ranges from 15mm to 25 mm, the included angle theta of the radiation baffle main bodies ranges from 50 degrees to 70 degrees, and the height h of the radiation plates ranges from 30 mm to 50 mm. In the invention, preferably, if a V-shaped baffle is adopted, the distance a between adjacent radiation baffle main bodies is 15mm, the included angle θ of the radiation baffle is 120 °, and the height h is 40mm; if the shutter type baffle is adopted, the distance a between the adjacent radiation baffles is 20mm, the inclination angle theta of the baffle is 60 degrees, and the height h is 40mm.
In particular to the present example, a V-shaped baffle is employed because the divertor particle removal apparatus 7 faces the high temperature surface of the divertor 2, the amount of external radiant heat is large, and the pumping speed can be increased by increasing the liquid helium flow rate. Each radiation shield is perforated with a central opening for connection to a liquid nitrogen line 17, the liquid nitrogen line 17 cooling the radiation shield 28 by means of heat conduction. The radiation shield 28 is made of pure copper and is surface-blackened to absorb external heat radiation as much as possible and prevent excessive radiation heat from being reflected to the low temperature adsorption plate 25. The arrangement mode, shape structure, size and quantity of the low-temperature adsorption plates can be flexibly adjusted according to the space of the upper window neck pipes of different tokamak vacuum chambers and the working requirement.
As shown in fig. 4 and 5, the low-temperature adsorption plate 25 includes a plurality of low-temperature adsorption plate main bodies, the two side surfaces of the low-temperature adsorption plate main body are all bonded with coconut shell activated carbon for adsorbing gas particles, and specifically adopt inorganic glue for bonding, and the inorganic glue is radiation-resistant compared with rubber, applicable in fusion neutron and gamma radiation environments, and effectively prolongs the service life of particle removal equipment. And the low-temperature adsorption plate main body is provided with a through hole communicated with the liquid helium pipeline 18 along the length direction of the low-temperature adsorption plate main body. According to the actual requirements, in order to increase the adsorption area as much as possible and realize the maximization of space utilization in the narrow space of the cold shield 11, the whole low-temperature adsorption plates 25 are symmetrically distributed, the low-temperature adsorption plate main bodies and the wall surface of the cold shield 11 are arranged at a certain angle, and the low-temperature adsorption plates 25 are formed by 21 cuboid low-temperature adsorption plate main bodies with 2 sizes. Wherein, the smaller low temperature adsorption plate main body comprises 19 blocks, the length is 450mm, the width is 50mm, the larger low temperature adsorption plate main body comprises 2 blocks, the length is 450mm, and the width is 110mm.
In this embodiment, four cryoadsorption plate temperature sensors 27 are arranged on the cryoadsorption plate main body to detect the temperature change thereof, and when the cryoadsorption plate temperature sensors 27 show that the temperature rise of the cryoadsorption plate exceeds 2K, the temperature of the cryoadsorption plate is reduced by increasing the liquid helium flow according to actual conditions. The low-temperature adsorption plate main body is provided with a through hole along the length direction and used for being connected with the liquid helium pipeline 14, the through hole forms a cooling channel for liquid helium to flow, and the cooling channel is 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 the plurality of low temperature adsorption plate main bodies are respectively communicated with the liquid helium inlet pipe 18 and the liquid helium outlet pipe 19. That is, 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 pipe structure, the inner layer pipeline of the concentric pipe 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 benefits of the double-layer concentric tube structure are: the outer annular outlet pipeline can play a role in heat insulation protection for the inner inlet pipeline. And a part of the main body of the low-temperature adsorption plate is connected with the liquid helium pipeline 14 in parallel, and the other part of the main body of the low-temperature adsorption plate 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 adsorption plates are connected in series, the temperature of the low-temperature adsorption plate 25 at the back of the series line is higher, and all the adsorption plates are connected in parallel, the flow of the liquid helium in each adsorption plate 25 is reduced, which is also not beneficial to cooling the adsorption plates; the series-parallel connection mode needs to be designed and optimized through temperature distribution analysis and integral pressure drop analysis of the low-temperature adsorption plate 25; the inlet and the outlet of the liquid helium pipeline 14 adopt 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 the 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.
And low-temperature sensors are respectively arranged at the inlet and outlet pipelines of the liquid helium pipeline 14 to detect temperature changes. As shown in fig. 4 and 6, the liquid nitrogen pipeline 17 has a liquid nitrogen inlet pipeline 13 and a liquid nitrogen outlet pipeline 15 in common, and the liquid nitrogen inlet pipeline 13 and the liquid nitrogen outlet pipeline 15 are divided into different branches to be connected with and cool the bottom plate 21, the cold screen 11 and the radiation baffle 28. Specifically, the liquid nitrogen pipeline 17 includes a pipeline main body penetrating through the radiation baffle 28 and attached to the inner wall of the cold shield 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 to the liquid nitrogen inlet pipeline 13 and the flow channel 23.
Fig. 2 is a partially enlarged view of a supporting portion of the divertor particle elimination apparatus 7. The divertor particle removal apparatus 7 is connected to the support flange 6 by three gravity supports 16 in a bolted connection; the supporting flange 6 is connected with the flange 4 of the upper window neck pipe cover plate of the vacuum chamber through a positioning supporting cylinder 10 in a vacuum brazing mode. Three through holes are arranged on the window neck tube cover plate flange 4 on the vacuum chamber and are respectively used for penetrating through a double-layer concentric pipeline of a liquid helium pipeline 14, a liquid nitrogen inlet pipeline 13 and a liquid nitrogen outlet pipeline 15. In order to seal the gap between the through hole and the pipeline, a vacuum bellows 5 is respectively welded with a window neck tube cover plate flange 4 on the vacuum chamber and the pipeline. The sealing mode of the vacuum bellows can absorb the thermal strain of the double-layer concentric pipeline caused by temperature cycle change, reduce the cyclic thermal stress on the double-layer concentric pipeline and effectively prolong the fatigue life of the liquid helium pipeline 14. The part of the double-layer concentric pipeline exposed to the environment of the Tokamak vacuum chamber is surrounded by the cold shield sleeve 9, so that the double-layer concentric pipeline is prevented from being subjected to the heat radiation of the upper window neck pipe 3 of the vacuum chamber and the cover plate flange 4 of the upper window neck pipe of the vacuum chamber. 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 work flow of the Tokamak divertor particle removal equipment is as follows:
and in the air exhaust starting stage, the divertor particle removal 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 removal equipment normally works (air extraction), in the working stage, the temperature of the low-temperature adsorption plate 25 is monitored through the 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 needs to be increased, so that the stability of the air extraction performance of the divertor particle removal equipment is ensured. When the pumping speed is decreased to 50% of the normal value, the divertor particle removal apparatus is regenerated to desorb and discharge the gas particles on the low temperature adsorption plate 25. Regeneration is divided into two modes: normal operation regeneration and regeneration after accident condition. In the normal operation and regeneration process, the liquid nitrogen pipeline 17 keeps the 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 through 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. The divertor particle removal equipment is regenerated after the leakage of cooling water or the exposure of air occurs inside the regeneration dacarbazick vacuum chamber 5 under the accident condition, and the activated carbon on the low-temperature adsorption plate 25 is easy to absorb water and poison under the accident condition, so deep regeneration is needed. In the deep regeneration process, liquid nitrogen and liquid helium need to be discharged simultaneously, the electric heating wire 12 is used for heating the cold screen 11 to about 500K, and the heat radiation of the cold screen 11 is used for heating the low-temperature adsorption plate 25. After the regeneration phase is completed, the above-mentioned cooling process is repeated, and the divertor particle removal apparatus can be put into operation again. When the divertor particle removal equipment needs to be maintained, the bolts of the upper window neck pipe cover plate flange 4 on the vacuum chamber are removed, and the upper window neck pipe cover plate flange 4 and the divertor particle removal equipment 7 are hoisted out together by a crane.
Compared with the prior art, the invention has the advantages that:
1. the low-temperature adsorption-based plug-in type tokamak divertor particle removal equipment has simple and independent installation and disassembly processes and convenient maintenance, and does not need to dismantle other interior parts of the tokamak vacuum chamber;
2. the plug-in Tokamak divertor particle removal equipment based on low-temperature adsorption adopts liquid helium for circulating cooling, has large refrigerating capacity, and can improve the pumping speed and the pumping capacity of the plug-in Tokamak divertor particle removal equipment by increasing the flow rate of the liquid helium and reducing the temperature of a liquid helium inlet;
3. compared with a low-temperature condensation method, the plug-in Tokamak divertor particle removal equipment based on low-temperature adsorption adopts a low-temperature adsorption air extraction method, so that the sensitivity to temperature change is low, the risk of particle analysis backflow can be reduced, the disturbance to plasma is reduced, and long-pulse discharge is ensured;
4. the adsorbent of the plug-in type tokamak divertor particle removal equipment based on low-temperature adsorption is bonded by inorganic glue, and the inorganic glue is radiation-resistant compared with rubber, can be suitable for fusion neutron and gamma radiation environments, and effectively prolongs the service life of the particle removal equipment;
5. the plug-in type tokamak divertor particle removing equipment based on low-temperature adsorption does not comprise a moving part, has the advantage of magnetic resistance, and can stably work in a strong magnetic field environment of tokamak.
The above description is only a preferred embodiment of the present invention, and it should be noted that, for those skilled in the art, many modifications and substitutions can be made without departing from the technical principle of the present invention, and these modifications and substitutions should also be regarded as the protection scope of the present invention.

Claims (9)

1. The utility model provides a tokamak divertor particle gets rid of equipment, installs in the real empty room upper window neck of tokamak, its characterized in that: including cold screen, liquid nitrogen pipeline, liquid helium pipeline, the bottom of cold screen is equipped with radiation baffle, the upper end of cold screen is equipped with the bottom plate, the liquid nitrogen pipeline sets up the inner wall of cold screen, just radiation baffle reaches the bottom plate all with the liquid nitrogen pipeline is connected, the inside of cold screen be equipped with the low temperature adsorption plate that the liquid helium pipeline is linked together.
2. The tokamak divertor particle exclusion apparatus of claim 1, wherein: the low temperature adsorption plate comprises a plurality of low temperature adsorption plate main bodies, activated carbon is arranged on two sides of each low temperature adsorption plate main body, and through holes communicated with the liquid helium pipeline are formed in each low temperature adsorption plate main body along the length direction of the low temperature adsorption plate main body.
3. The tokamak divertor particle exclusion apparatus of 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 into 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. The tokamak divertor particle exclusion apparatus of 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. The tokamak divertor particle exclusion apparatus of claim 1, wherein: the bottom plate is provided with a flow channel communicated with a liquid nitrogen pipeline, and the upper cover of the flow channel is closed with a cover plate.
6. The tokamak divertor particle exclusion apparatus of claim 5, wherein: the liquid nitrogen pipeline comprises a pipeline main body, a liquid nitrogen inlet pipeline and a liquid nitrogen outlet pipeline, wherein the pipeline main body penetrates through the radiation baffle and is attached to the inner wall of the cold shield, the liquid nitrogen outlet pipeline is 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. The tokamak divertor particle exclusion apparatus of claim 1, wherein: the radiation baffle comprises a plurality of radiation baffle bodies which are arranged at intervals in sequence, the cross section of each radiation baffle body is V-shaped, or the radiation baffle bodies are arranged according to a shutter type.
8. The tokamak divertor particle exclusion apparatus of claim 7, wherein: the range of the distance a between the adjacent V-shaped radiation baffle main bodies is 10-20 mm, the range of the included angle theta of the radiation baffle main bodies is 110-130 degrees, and the range of the height h of the radiation plate is 30-50 mm; the distance a between adjacent louver type radiation baffle main bodies ranges from 15mm to 25 mm, the included angle theta of the radiation baffle main bodies ranges from 50 degrees to 70 degrees, and the height h of the radiation plates ranges from 30 mm to 50 mm.
9. The tokamak divertor particle exclusion apparatus of claim 1, wherein: the outer wall of the cold shield is wound with a heating wire, and the outer wall of the cold shield is provided with a cold shield temperature sensor.
CN202210951177.4A 2022-08-09 2022-08-09 Tokamak divertor particle removal equipment Active CN115295176B (en)

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CN115295176B CN115295176B (en) 2023-06-02

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