CN116189924B - Particle elimination structure and method for meeting kilosecond order plasma - Google Patents
Particle elimination structure and method for meeting kilosecond order plasma Download PDFInfo
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- CN116189924B CN116189924B CN202310461978.7A CN202310461978A CN116189924B CN 116189924 B CN116189924 B CN 116189924B CN 202310461978 A CN202310461978 A CN 202310461978A CN 116189924 B CN116189924 B CN 116189924B
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- G—PHYSICS
- 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
- G21B1/11—Details
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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 discloses a particle elimination structure and a method for realizing kilosecond-level plasma, comprising an increased particle elimination channel between a divertor target plate and a Dome plate and an advanced plasma configuration control technology, which can reduce the particle elimination path; the high pumping speed and annular cryopump is arranged in a vacuum chamber of the fusion device, and the high-capacity external cryopump is arranged on the top and bottom windows of the device, so that the pumping capability of particles can be improved. In the high-temperature plasma discharge process of the fusion device, an advanced plasma control technology is utilized to optimize the plasma configuration, so that the striking point falls on the horizontal target plate of the divertor, the distance from the particles to the extraction opening of the divertor is shortened, the discharge path of the particles is further shortened, and the particle removal efficiency is improved; the combination of the high pumping speed, the annular internal low-temperature pump and the high-capacity external low-temperature pump improves the pumping speed and the long-time steady pumping capacity of particles in kilosecond-level plasma discharge.
Description
Technical Field
The invention relates to the field of fusion reactors, in particular to a particle elimination structure and a particle elimination method for thousands of seconds of plasmas.
Background
Energy is the basis for the maintenance and development of human civilization. The magnetic confinement thermonuclear fusion energy with high efficiency, cleanness, safety and rich raw materials can be said to be the best way for solving the energy crisis by human beings. The comprehensive construction of the international thermonuclear fusion experimental reactor (ITER) provides unprecedented opportunities for magnetorestrictive thermonuclear fusion research.
The effective elimination of particles is a key scientific problem affecting the operation of tokamak, and is an important guarantee for obtaining the operation of long-pulse high-parameter plasmas. In the plasma discharge process in the fusion device, impurities and fuel particles are transported from the core part to the outside, enter a partial filter area through a scraping layer under the guidance of magnetic lines of force and are neutralized, the partial filter gathers and collects the neutralized particles, and a particle removal system is required to rapidly discharge neutral gas out of plasma in real time. For steady-state operation of long pulse plasmas, efficient exclusion of divertor particles is critical to stable control of long pulse density, avoiding plasma rupture due to density limits.
In order to improve the particle removal efficiency, a vacuum pump set with a larger pumping speed and a larger number of vacuum pump sets are generally used, including a molecular pump, a cryopump and the like. The molecular pump has smaller compression ratio to small molecular hydrogen isotopes, so the pumping speed to the fuel particle hydrogen isotopes is smaller. Meanwhile, in a future fusion device, the working air pressure at the position of the divertor is 1-10Pa, so that the particle removal efficiency of the molecular pump is greatly reduced. The cryopump realizes powerful adsorption of impurities and fuel gas by utilizing a low-temperature condensation and adsorption mode. However, because the working medium of fusion plasma is hydrogen isotope, and the pumping capacity of a common low-temperature pump is limited, the device cannot meet the requirements of practical use, and various hydrogen-pumping type low-temperature pumps are developed according to the requirements of various devices. On the basis of improving the pumping capacity of the vacuum pump, the size of the conductance of the neutral particle removal path and the length of the particle discharge path in the divertor position are also important, since the pumping speed of the vacuum pump depends on the pumping speed of the pump and the conductance of the pumping pipe.
In the long pulse discharge of fusion devices, a single technical upgrade cannot meet the requirement of long-time discharge particle discharge. In eastern ultra-loop (EAST) fusion devices, it has been found that simply by adding a divertor particle discharge channel, the precedent that the discharge can not be taken away in time for a long time to generate particles is that when the striking point is controlled at the divertor vertical target plate, the neutral pressure of the divertor is larger when the striking point is far away from the particle discharge channel, resulting in the particles flowing back to the plasma. At the same time, commercial cryopumps also fail to meet the particle pumping speed requirements, there are small pumping speeds (about 10m for hydrogen 3 S), small capacity (25 standard liters), and the problems of insufficient pumping speed and capacity are obviously observed in the discharge of the EAST device; as the discharge proceeds, the low Wen Bengxi particle attachment capability gradually weakens, and finally reaches saturation and gas release into the plasma discharge vacuum chamber, so that the plasma discharge density is uncontrollable, and long pulse steady state operation cannot be maintained.
Disclosure of Invention
The invention aims to make up the defects of the prior art, and provides a particle elimination structure and a particle elimination method for thousands of seconds of plasmas, so as to solve the problem of steady-state operation density control of long-pulse plasmas of a fusion reactor device in the future.
The invention is realized by the following technical scheme:
a particle elimination structure meeting the kilosecond order plasma comprises an inner target plate of a divertor, an outer target plate of the divertor, a Dome plate of the divertor, inner and outer striking points, an upper and lower built-in cryopump, a gate valve and an external cryopump; the fusion device is a magnetic confinement plasma discharge facility, the plasma is in a vacuum chamber in the fusion device, the inner target plate of the divertor, the outer target plate of the divertor and the date plate of the divertor form a divertor in the fusion device together, and divertor particle discharge channels are respectively arranged among the inner target plate of the divertor, the outer target plate of the divertor and the date plate of the divertor; the inner and outer striking points are the action areas of the plasmas, the inner target plate of the divertor and the outer target plate of the divertor, the upper and lower built-in low-temperature pumps are arranged on the vacuum chamber wall of the fusion device and positioned on the back surface of the outer target plate of the divertor, and the gate valve is vacuum isolation equipment of the external low-temperature pumps and the vacuum chamber of the fusion device; the external cryogenic pump is arranged on the top and bottom pipelines of the fusion device.
Further, two inner and outer striking points of the plasma fall on an inner target plate of the divertor and an outer target plate of the divertor respectively, a large amount of particles enter the divertor and are neutralized in the plasma discharging process, and the divertor gathers and collects the neutralized particles.
Further, the size of the particle discharge channel of the divertor is nearly doubled compared with the original particle discharge channel, and the particle discharge efficiency is improved.
Further, the surface area of the internal active carbon and the low-temperature cold quantity of the external low-temperature pump are increased, and the capacity and the pumping speed of the external low-temperature pump are improved.
Further, the plasma is formed by collecting ions, electrons and non-ionized neutral particles, and is in a neutral substance state and is confined in the fusion device.
The invention also provides a particle elimination method of the particle elimination structure meeting the kilosecond order plasma, which comprises the following steps:
step 1: increasing the gap between the inner and outer divertor target plates and the divertor home plate, thereby increasing the size of the divertor particle discharge channel;
step 2: the advanced plasma control technology comprising an electromagnetic measurement integrator signal drift calibration technology under an ultra-long time scale and a complete non-inductive plasma current drive feedback control technology is utilized to optimize the configuration of a divertor in plasma discharge, so that an inner striking point and an outer striking point fall on a horizontal target plate of the divertor, wherein the horizontal target plate is a horizontal part of an inner target plate of the divertor and an outer target plate of the divertor, the distance from particles to an extraction opening of the divertor is shortened, and the particle removal efficiency is improved; the advanced plasma control technology realizes the precise control of the configuration of the divertor, realizes the precise control of X points and inner and outer striking points, wherein the X points refer to magnetic field zero points, and controls the inner and outer striking points of the divertor at a position closer to a divertor particle discharge channel, thereby shortening the discharge path of the divertor particles;
step 3: the high pumping speed annular internal low-temperature pump and the high-capacity external low-temperature pump are utilized to provide the discharge speed and capacity of particles, and the pumping speed of the particles in kilosecond-order plasma discharge and the capability of removing the particles in long-time steady state are improved.
Further, the annular built-in low-temperature pump with high pumping speed is arranged in the fusion device and is arranged on the vacuum chamber wall at the back of the divertor, and the pipeline of the built-in low-temperature pump is cooled to below 10K by utilizing a low-temperature condensation mode, so that the powerful adsorption of impurities and fuel gas is realized; the external low-temperature pump is arranged on windows at the top and the bottom of the fusion device, and the capacity and the pumping speed of the external low-temperature pump are improved by increasing the surface area of active carbon and the low-temperature cold quantity in the cold pump.
Furthermore, the large pumping speed and annular built-in cryogenic pump is arranged inside the fusion device, so that the pumping path is greatly reduced, the pumping conductance is increased, and meanwhile, the pumping speed is high due to the large surface area, and the pumping requirement of high-flow gas is met. The external cryogenic pump is arranged on the top window and the bottom window of the fusion device, and the capacity and the pumping speed of the external cryogenic pump are improved by increasing the surface area of active carbon in the cryogenic pump, the low-temperature cold quantity and the like, so that the unsaturation in thousands of seconds of plasma discharge of the cryogenic pump is ensured.
The particle elimination method meeting the requirement of kilosecond-level plasma is a cooperative control method of the three technologies, firstly, an advanced plasma control technology is used for enabling plasma striking points to be accurately controlled to a horizontal target plate of a divertor, and therefore neutralized fuel particles are closer to a particle elimination channel of the divertor and have larger conductance; simultaneously discharging particles collected on the horizontal target plate of the divertor out of the divertor region in cooperation with the increased divertor particle discharge channel; finally, the particles are timely pumped and stored for a long time by the combination of the back of the divertor and an external cold pump with large capacity and high pumping speed. Through the cooperation of the three technologies, the clearance path of the particles in the limited space dimension of the tokamak is ensured to be smooth, the continuous clearance and collection of the plasma particles in a long time dimension are ensured, and the particle reflux is reduced. The fusion device is a magnetic confinement fusion reactor device, hydrogen isotope gas is confined in a special magnetic container by using a strong magnetic field and heated to a high temperature of billions of DEG C to realize fusion reaction, and energy is released.
The particles comprise impurities and fuel particles, wherein the impurities mainly come from release of wall materials, leakage of air and water and the like, and the fuel particles are hydrogen isotopes, hydrogen, deuterium and tritium.
In the long pulse plasma discharge process of the fusion device, the structure controls the inner and outer striking points in the area close to the extraction opening of the divertor by utilizing the accurate control technology of the plasma configuration, and the effective removal of particles is realized by increasing the exhaust channel of the divertor, reducing the particle discharge path, and a low-temperature pump with built-in high pumping speed and external high capacity.
The invention has the advantages that:
the invention adopts three modes of increasing the design of the air suction flow guide of the divertor, reducing the discharge path of particles and improving the air suction capacity of the cryopump to cooperatively work, thereby improving the particle discharge efficiency in kilosecond-level plasma discharge. In the high-temperature plasma discharge process of the fusion device, designing an increased gap between a target plate and a Dome plate of a divertor, increasing a discharge channel of particle flow at the position of the divertor, and further increasing the pumping air flow guide; the striking point is enabled to fall on the horizontal target plate of the divertor by utilizing an advanced plasma control technology, so that the distance from particles to the extraction opening of the divertor is shortened, and the discharge path of the particles is shortened; the combination of the high pumping speed, the annular internal low-temperature pump and the high-capacity external low-temperature pump is utilized to improve the pumping speed and the long-time steady pumping capacity of particles in kilosecond-level plasma discharge.
Drawings
FIG. 1 is a schematic illustration of a particle exclusion configuration for a kilosecond-scale plasma of the present invention;
in the figure: 1-fusion device, 2-plasma, 3-partial filter inner target plate, 4-partial filter outer target plate, 5-partial filter Dome plate, 6-internal and external striking points, 7-up and down built-in cryopump, 8-gate valve, 9-external cryopump, 10-partial filter particle discharge channel.
Detailed Description
The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention, and it is apparent that the described embodiments are only some embodiments of the present invention, but not all embodiments, and all other embodiments obtained by those skilled in the art without the inventive effort based on the embodiments of the present invention are within the scope of protection of the present invention.
As shown in FIG. 1, the particle eliminating structure for thousands of second order plasma comprises an inner target plate 3 of a divertor, an outer target plate 4 of the divertor, a Dome plate 5 of the divertor, an inner striking point 6, an upper and lower built-in cryopump 7, a gate valve 8 and an external cryopump 9. The fusion device 1 is a magnetic confinement plasma discharge facility, the plasma 2 is in a vacuum chamber in the fusion device 1, the inner target plate 3 of the divertor, the outer target plate 4 of the divertor and the date plate 5 of the divertor form a divertor in the fusion device 1 together, and a divertor particle discharge channel 10 is respectively arranged between the inner target plate 3 of the divertor, the outer target plate 4 of the divertor and the date plate 5 of the divertor. The inner and outer striking points 6 are important action areas of the plasma 2, the inner target plate 3 of the divertor and the outer target plate 4 of the divertor, the upper and lower built-in cryopumps 7 are arranged on the vacuum chamber wall of the fusion device 1, the rear of the outer target plate 4 of the divertor, and the gate valve 8 is vacuum isolation equipment between the external cryopump 9 and the vacuum chamber of the fusion device 1.
The fusion device 1 as a key component comprises a divertor inner target plate 3, a divertor outer target plate 4 and a divertor Dome plate 5, wherein two inner and outer striking points 6 of plasma respectively fall on the divertor inner target plate 3 and the divertor outer target plate 4, a large number of particles enter a divertor region and are neutralized in the discharging process of the plasma 2, and the divertor gathers and collects the neutralized particles; the novel divertor increases the gap between the divertor inner target plate 3 and the divertor Dome plate 5 and between the divertor outer target plate 4 and the divertor Dome plate 5, namely increases the divertor particle discharge channel 10, the current optimized particle discharge channel is about 53mm, which is nearly doubled compared with the original particle discharge channel (28 mm), and the particle discharge efficiency is improved.
The upper and lower built-in cryopump 7 serving as a key component is arranged inside the fusion device 1 and is arranged on the vacuum chamber wall on the back surface of the outer target plate 4 of the divertor, so that the particle removal path is greatly reduced, and the air extraction capability is improved. The external low-temperature pump 9 serving as a key component is arranged on the top and bottom pipelines of the fusion device 1, and the capacity and pumping speed of the external low-temperature pump 9 are improved by increasing the surface area of active carbon in the external low-temperature pump 9, low-temperature cold energy and the like.
The fusion device 1 as a key component is a magnetic confinement fusion reactor device, and adopts a spiral magnetic field to confine the plasma 2 of hydrogen isotopes inside the fusion device 1, so that a large amount of nuclear fusion reactions can be controllably generated, and energy is released.
The plasma 2, which is a key component, is composed of a collection of ions, electrons and unionized neutral particles, and is entirely in a neutral state and is confined in the magneto-confined fusion device.
The specific working flow of the particle elimination method for the kilosecond-level plasma is as follows: firstly, designing gaps among an enlarged divertor inner target plate 3, a divertor outer target plate 4 and a divertor Dome plate 5, and increasing discharge channels of particle flows at the divertor position, so as to increase pumping conductance; the inner and outer striking points 6 are precisely controlled to the area of the divertor target plate near to the divertor particle discharge channel 10 by utilizing advanced plasma control technology, including electromagnetic measurement integrator signal drift calibration technology under ultra-long time scale and complete non-inductive plasma current drive feedback control technology, so as to reduce the discharge path of particles; using a large pumping speed, annular built-in cryopump (pumping speed about 70m 3 S) and a high-capacity external cryopump 9 (100 standard liters), and improves the pumping speed and long-time steady pumping capability of particles in kilosecond-level plasma discharge. By utilizing the synergistic effect of the three modes, the particle removal efficiency in kilosecond-level plasma discharge is improved.
While the foregoing has been described in relation to illustrative embodiments thereof, so as to facilitate the understanding of the present invention by those skilled in the art, it should be understood that the present invention is not limited to the scope of the embodiments, but is to be construed as limited to the spirit and scope of the invention as defined and defined by the appended claims, as long as various changes are apparent to those skilled in the art, all within the scope of which the invention is defined by the appended claims.
Claims (5)
1. A particle exclusion structure for a kilosecond-level plasma, characterized by: the device comprises an inner target plate of a divertor, an outer target plate of the divertor, a home plate of the divertor, inner and outer striking points, an annular upper and lower built-in cryopump with high pumping speed, a gate valve and an external cryopump; the fusion device is a magnetic confinement plasma discharge facility, the plasma is in a vacuum chamber in the fusion device, the inner target plate of the divertor, the outer target plate of the divertor and the date plate of the divertor form a divertor in the fusion device together, and divertor particle discharge channels are respectively arranged between the inner target plate of the divertor and the date plate of the divertor and between the outer target plate of the divertor and the date plate of the divertor; the inner and outer striking points are the action areas of the plasmas, the inner target plate of the divertor and the outer target plate of the divertor, the upper and lower built-in low-temperature pumps are arranged on the vacuum chamber wall of the fusion device and positioned on the back surface of the outer target plate of the divertor, and the gate valve is vacuum isolation equipment of the external low-temperature pumps and the vacuum chamber of the fusion device; the external cryogenic pump is arranged on the top and bottom pipelines of the fusion device;
the particle discharge channel of the divertor is 53mm, so that the particle discharge efficiency is improved;
the surface area of the internal active carbon and the low-temperature cold capacity of the external low-temperature pump are increased, and the capacity and the pumping speed of the external low-temperature pump are improved.
2. A particle excluding structure satisfying a plasma of the order of kiloseconds according to claim 1, characterized in that: the inner and outer striking points of the plasma fall on an inner target plate of the divertor and an outer target plate of the divertor respectively, a large number of particles enter the divertor and are neutralized in the plasma discharging process, and the divertor gathers and collects the neutralized particles.
3. A particle excluding structure satisfying a plasma of the order of kiloseconds according to claim 1, characterized in that: the plasma is formed by the aggregation of ions, electrons and non-ionized neutral particles, and is in a neutral substance state and is restrained in the fusion device.
4. A particle excluding method satisfying a particle excluding structure of a plasma of the order of kiloseconds according to one of claims 1 to 3, characterized by comprising the steps of:
step 1: increasing the gap between the inner and outer divertor target plates and the divertor home plate, thereby increasing the size of the divertor particle discharge channel;
step 2: optimizing the configuration of a divertor in plasma discharge by utilizing an advanced plasma control technology comprising an electromagnetic measurement integrator signal drift calibration technology under an ultra-long time scale and a complete non-inductive plasma current drive feedback control technology, so that inner and outer striking points fall on a divertor horizontal target plate, the distance from particles to an extraction opening of the divertor is shortened, and the particle removal efficiency is improved; the advanced plasma control technology is used for realizing the precise control of the configuration of the divertor and the precise control of an X point and an inner striking point and an outer striking point, wherein the X point refers to a magnetic field zero point, the inner striking point and the outer striking point of the divertor are controlled at a position closer to a divertor particle discharge channel, and the discharge path of the divertor particles is shortened;
step 3: the annular built-in low-temperature pump with high pumping speed and the high-capacity external low-temperature pump are combined to provide the discharge speed and capacity of particles, so that the pumping speed of the particles in kilosecond-level plasma discharge and the capability of removing the particles in long-time steady state are improved;
the step 1, the step 2 and the step 3 are performed with indispensable coordination, firstly, an advanced plasma control technology is used for accurately controlling the plasma striking point to the horizontal target plate of the divertor, and simultaneously, particles accumulated on the horizontal target plate of the divertor are discharged out of the divertor area by matching with an increased divertor particle discharge channel; finally, the particles are timely pumped and stored for a long time by combining a ring-shaped internal low-temperature pump with high pumping speed and a high-capacity external low-temperature pump; through the cooperation, the clearance path of the particles in the limited space of the tokamak is ensured to be smooth, the continuous clearance and collection of the plasma particles in a long time scale are ensured, and the particle reflux is reduced.
5. A particle excluding method for satisfying a plasma of the order of kiloseconds according to claim 4, characterized in that:
the annular built-in low-temperature pump with high pumping speed is arranged inside the fusion device, and the pipeline of the built-in low-temperature pump is cooled to below 10K by utilizing a low-temperature condensation mode, so that the powerful adsorption of impurities and fuel gas is realized.
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| CN116189924A (en) | 2023-05-30 |
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