CN1112710C - Electric field drifting electron injection method and device for increasing fusion plasma restraint performance - Google Patents

Electric field drifting electron injection method and device for increasing fusion plasma restraint performance Download PDF

Info

Publication number
CN1112710C
CN1112710C CN96117141A CN96117141A CN1112710C CN 1112710 C CN1112710 C CN 1112710C CN 96117141 A CN96117141 A CN 96117141A CN 96117141 A CN96117141 A CN 96117141A CN 1112710 C CN1112710 C CN 1112710C
Authority
CN
China
Prior art keywords
electric field
electron
bottom crown
injector
plasma
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Fee Related
Application number
CN96117141A
Other languages
Chinese (zh)
Other versions
CN1180901A (en
Inventor
潘垣
刘保华
姜书方
宁成
李建刚
汪茂泉
毛剑珊
阎晓林
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Institute of Plasma Physics of CAS
Original Assignee
Institute of Plasma Physics of CAS
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Institute of Plasma Physics of CAS filed Critical Institute of Plasma Physics of CAS
Priority to CN96117141A priority Critical patent/CN1112710C/en
Publication of CN1180901A publication Critical patent/CN1180901A/en
Application granted granted Critical
Publication of CN1112710C publication Critical patent/CN1112710C/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Classifications

    • 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

Abstract

The present invention relates to an electric field drifting electron injection method and a device for improving the restraint performance of fusion plasma. The comprises that an electric field traverses a magnetic field by drifting to inject charged particles, a radical electric field is generated to realize a controllable H mould. The cavity of an electron injector for realizing the method of the present invention is connected with a main vacuum chamber of a tokamak device and a lower pole plate, a cathode is fixed on the lower pole plate, and the electron injector is provided with an upper pole plate corresponding to the lower pole plate. The device for realizing the method of the present invention is an electric field drifting electron injector of which the intensity of flow is controllable, and the electric field drifting injector not only can inject electrons, but also inject other charged particles.

Description

Improve the electric field drifting electron injection method and the device of fusion plasma restraint performance
Technical field:
The present invention relates to the controlled nuclear fusion engineering.
Background technology:
The height of tokamak fusion reactor plasma constraint mould (H mould) is the important operational mode of the magnetic confinement controlled nuclear fusion heap that will emerge in the beginning of next century.Adopt multiple heater means or bias electrode method on many tokamak, all successfully to realize the H mould so far in the world.But the H mould that adopts heater means to realize is spontaneous formation, can not be also uncontrollable lastingly.The H mould that adopts the bias electrode method to realize has been introduced a large amount of impurity to plasma.
The constraint of plasma always is the core of controlled nuclear fusion research.Be found from the H mould, after the researchist recognizes the vital role of radial electric field in the H mould changes, just studying a kind of magnetic field article on plasma of crossing of searching always and charging (injection charged particle), produce radial electric field, realize the effective ways of controlled H mould.
United States Patent (USP) Patent Number:5,225,146; Date of Patent:199376, inventor: the director of plasma physics National Laboratory of the former U.S. of Masayuki Ono and Harold Furth Pu Linsideng university, world-renowned plasma physics and nuclear fusion scientist, a kind of electronics injection method is proposed, be to inject electronics to Tokamak Plasma by the gradient B drift principle, make plasma electronegative and set up radial electric field in its marginarium, and the angle (utmost point to) that makes down plasma generation have shear property in this radial electric field and device magnetic field (hoop) effect rotates, thereby improve the restraint performance of plasma, realize the H mould.But the electron capture of this method in order to make electronics radially float to plasma slab and will drift about and needs to add magnet in electronics inlet both sides, and this magnetic field superposition that adds the magnet generation forms the regional area ripple field of trapped electrons on the former magnetic field of device.This magnetic field that adds magnet on effect as stray magnetic field, will inevitably destroy the axial symmetry of tokamak toroidal magnetic field and influence the magnetic field configuration of tokamak greatly, thereby plasma restraint performance will be descended, this spinoff certainly will reduce the actual effect of this electronics method for implanting greatly.
Summary of the invention:
Technical matters to be solved by this invention is, overcomes existing gradient B drift and injects the deficiency that electronic method exists, and a kind of electronics injection method and device that can improve fusion plasma restraint performance is provided.
The method that the present invention solves the problems of the technologies described above is, adds a controlled electric field in the main plasma outside vertical on tokamak device longitudinal magnetic field direction, utilizes electrical drift to be injected in the plasma by the electron drift that emission of cathode is come out.In brief, the inventive method is crossed magnetic field by electrical drift exactly, injects charged particle.
The inventive method does not influence the magnetic field configuration of confining plasma, also can inject the tetanic control edge plasma radial electric field that connects of stream of charged particle by control, can steady-state operation be easy to FEEDBACK CONTROL again.
The present invention solves that the technical solution of existing technical matters is in the background technology, a kind of electric field drifting electron injection device---electron injector of the raising fusion plasma restraint performance according to method of the present invention design, it is characterized in that: the main vacuum chamber of electron injector cavity and tokamak device links, the electron injector cavity links to each other with bottom crown, the electric electron injector cavity of going up, the electron injector bottom crown all is in identical earth potential with the main vacuum chamber of tokamak device, mechanically negative electrode is fixed on the bottom crown, the electric minus plate of going up insulate with bottom crown, be arranged in bottom crown directly over.
The present invention has following outstanding advantage and significant effect:
After electronics injected, plasma was electronegative, and set up the negative radial electric field with shearing in edge plasma, thereby made the plasma generation utmost point to rotation, formed to transport and built layer, improved the restraint performance of plasma, entered the operation of H mould.The present invention except that the negative electrode of emitting electrons, no longer needs specific anode and control grid in the electronics injection process, do not influence the magnetic field configuration and the balance of plasma.Electronics of the present invention injects and can be controlled, and electron injector not only can inject electronics, also can inject other charged particle.
Description of drawings:
Figure of description is the electric field drifting electron injection device of raising fusion plasma restraint performance of the present invention---the structural representation of a preferred embodiment of electron injector.
Embodiment:
As shown in drawings, electron injector cavity 1 links to each other with bottom crown 4, and electron injector cavity 1 links to each other with the main vacuum chamber 5 of tokamak device, makes bottom crown 4 be in identical earth potential with main vacuum chamber 5 like this, and electron injector cavity 1 is in identical vacuum condition with main vacuum chamber 5; Mechanically negative electrode 2 is fixed on the bottom crown 4, and the angle of its intersection is 30 °～45 °, and negative electrode 2 insulate on electric with bottom crown 4; Top crown 3 with positive polarity be placed on bottom crown 4 directly over, top crown 3, bottom crown 4 and negative electrode 2 all can move on the one dimension horizontal direction.
Referring to accompanying drawing, during work, by the pulse positive high voltage being added on the top crown 3, during negative electrode 2 preheatings and top crown 3 do not add high pressure, make negative electrode add tens volts positive potential to suppress the cathode electronics emission as the adjustment pipe of switch, keep the interior insulativity of cavity 1.Top crown 3 adds high pressure, and when setting up electric field between last bottom crown, anticathode 2 must add 200～500 volts of negative potentials, and electronics is launched, and produces the strength of current of 75～100A.Because bottom crown 4 links with injector cavity 1, injector cavity 1 links with main vacuum chamber 5 again, so bottom crown 4 is in identical earth potential with main vacuum chamber 5, and injector cavity 1 is in identical vacuum condition with main vacuum chamber 5.When top crown 3 adds positive high voltage, between last bottom crown, produce electric field vertically downward, this electric field intensity can be controlled.Longitudinal magnetic field 7 is present in the tokamak main vacuum chamber 5 and main vacuum chamber 5 outsides, and described electric field and magnetic field are quadratures.The electronics that emits from negative electrode 2 is under the effect of this quadrature field, with drift velocity V → D = E → × B → / B 2 Level floats to left in the plasma 6, realizes 6 chargings of article on plasma body, produces radial electric field, and then realizes improving plasma 6 restraint performances by the H mould.

Claims (4)

1, a kind of electric field drifting electron injection method that improves fusion plasma restraint performance, it is characterized in that: on tokamak device longitudinal magnetic field direction, add a controlled electric field in the main plasma outside vertical, utilize electrical drift, will be injected in the plasma by the electron drift that emission of cathode is come out.
2, a kind of electric field drifting electron injection device---electron injector that improves fusion plasma restraint performance, it is characterized in that: the main vacuum chamber of electron injector cavity and tokamak device links, the electron injector cavity links to each other with bottom crown, electric upward electron injector cavity, electron injector bottom crown all are in identical earth potential with the main vacuum chamber of tokamak device, mechanically negative electrode is fixed on the bottom crown, the electric minus plate of going up insulate to bottom crown, top crown is the positive polarity high-field electrode, is arranged in the top that faces bottom crown.
3, injector as claimed in claim 2 is characterized in that: the angle of negative electrode and bottom crown intersection is 30 °～45 °.
4, injector as claimed in claim 2 is characterized in that: top crown, bottom crown and negative electrode all can move adjusting in the one dimension horizontal direction.
CN96117141A 1996-10-17 1996-10-17 Electric field drifting electron injection method and device for increasing fusion plasma restraint performance Expired - Fee Related CN1112710C (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN96117141A CN1112710C (en) 1996-10-17 1996-10-17 Electric field drifting electron injection method and device for increasing fusion plasma restraint performance

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN96117141A CN1112710C (en) 1996-10-17 1996-10-17 Electric field drifting electron injection method and device for increasing fusion plasma restraint performance

Publications (2)

Publication Number Publication Date
CN1180901A CN1180901A (en) 1998-05-06
CN1112710C true CN1112710C (en) 2003-06-25

Family

ID=5124076

Family Applications (1)

Application Number Title Priority Date Filing Date
CN96117141A Expired - Fee Related CN1112710C (en) 1996-10-17 1996-10-17 Electric field drifting electron injection method and device for increasing fusion plasma restraint performance

Country Status (1)

Country Link
CN (1) CN1112710C (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN100367413C (en) * 2005-01-27 2008-02-06 中国科学院等离子体物理研究所 Method and device for measuring corona current in Tokamak device
CN101189684B (en) * 2005-03-07 2013-04-24 加州大学评议会 Plasma electric generation system

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101093211B (en) * 2006-06-21 2010-05-12 中国科学院电子学研究所 Transient drift field method in use for drift tube of ionic mobility spectrometer
CN102708931B (en) * 2012-05-07 2015-05-20 华中科技大学 Electro beam ejection restraint method and device under strong magnetic field
CN106816182B (en) * 2016-12-20 2018-03-27 华中科技大学 One kind injection electron collector
CN106898385B (en) * 2017-03-06 2018-04-24 华中科技大学 Electronics gun-type electron-beam enters the apparatus and method of constraint under a kind of high-intensity magnetic field
CN108986928B (en) * 2018-07-24 2020-05-19 华中科技大学 Electron drift injection system
US11898798B1 (en) * 2022-09-01 2024-02-13 Limelight Steel Inc. High-efficiency photonic furnaces for metal production

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN100367413C (en) * 2005-01-27 2008-02-06 中国科学院等离子体物理研究所 Method and device for measuring corona current in Tokamak device
CN101189684B (en) * 2005-03-07 2013-04-24 加州大学评议会 Plasma electric generation system

Also Published As

Publication number Publication date
CN1180901A (en) 1998-05-06

Similar Documents

Publication Publication Date Title
Hughes et al. Three-dimensional calculations for a 4 kA, 3.5 MV, 2 microsecond injector with asymmetric power feed
CN1112710C (en) Electric field drifting electron injection method and device for increasing fusion plasma restraint performance
Stirling et al. 15 cm duoPIGatron ion source
Kuriyama et al. High energy negative-ion based neutral beam injection system for JT-60U
CA2440603A1 (en) Controlled fusion in a field reversed configuration and direct energy conversion
KR20200109324A (en) Accelerator and accelerator system
Mason et al. Magnetic field penetration of erosion switch plasmas
CN102708931B (en) Electro beam ejection restraint method and device under strong magnetic field
Hanada et al. Negative ion production in a large semicylindrical ion source
CN202563899U (en) Device for constraining electron beam injection under strong magnetic field
CN106816182B (en) One kind injection electron collector
Kuriyama et al. Construction of a 500 keV/negative-ion-based NBI system for JT-60U
Leitner et al. Development of the radio frequency driven H-ion source for the National Spallation Neutron Source
Azizov et al. Engineering-physical tokamak T-15MD and steady-state injection
Kaneko et al. Negative-ion-based neutral beam injector for Large Helical Device
Noda et al. Conceptual design of carbon/proton synchrotron for particle beam therapy
CN208094871U (en) A kind of treat uses proton-synchrotron
Okabe et al. Development of H-injection of proton-FFAG at KURRI
Henestroza et al. Beam Dynamics studies of the heavy ion fusion accelerator injector
Wessel et al. Intense, Neutralized-Ion Beam Heating of a MFE Plasma
Jinxiang et al. Investigation of ion sources and injector used in RFQ accelerator
Okano Beam driven tokamak fusion reactors
Ohara Progress of neutral beam R&D for plasma heating and current drive at JAERI
Stinnett et al. A magnetically insulated negative ion source for neutral beam heating
Ohara et al. Development of high power negative‐ion sources for fusion research at JAERI

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C14 Grant of patent or utility model
GR01 Patent grant
C19 Lapse of patent right due to non-payment of the annual fee
CF01 Termination of patent right due to non-payment of annual fee