CN104637549B - Tokamak Plasma ruptures electromagnetic energy deriving method and device - Google Patents
Tokamak Plasma ruptures electromagnetic energy deriving method and device Download PDFInfo
- Publication number
- CN104637549B CN104637549B CN201510055460.9A CN201510055460A CN104637549B CN 104637549 B CN104637549 B CN 104637549B CN 201510055460 A CN201510055460 A CN 201510055460A CN 104637549 B CN104637549 B CN 104637549B
- Authority
- CN
- China
- Prior art keywords
- energy
- plasma
- rupture
- vacuum chamber
- energy transfer
- 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.)
- Active
Links
Classifications
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma Technology (AREA)
Abstract
Alleviate method and device the invention discloses rupture derived from a kind of Tokamak Plasma rupture electromagnetic energy.This method is rupturing moment coupling plasma body portion electromagnetic energy using the energy transfer coil of one group and plasmon coupling, and export vacuum chamber and absorbed by energy absorbing member, can reduce rupture moment is dissipated in the summation of internal vacuum chamber energy, alleviates rupture transient plasma huge energy and is dissipated in the harm that internal vacuum chamber is caused.Existing a large amount of gas injection (Massive Gas Injection, the rupture alleviation method such as MGI), the summation that rupture process is dissipated in internal vacuum chamber energy can not be reduced, this method can effectively make up this defect, it can be cooperated with the method such as existing MGI, the common infringement for alleviating rupture plasma huge energy to device feature.This method does not need complicated technological means, and simple and reliable, cost of implementation is low, and a kind of Tokamak Plasma can be used as to rupture alleviation method.
Description
Technical field
The invention belongs to magnetic confinement nuclear fusion Plasma disruption protection field, and in particular to a kind of to be utilized in rupture moment
Plasma part electromagnetic energy is exported vacuum chamber by electromagnetic coupled, and reduction rupture moment is dissipated in internal vacuum chamber energy summation
Rupture alleviate method and its device.
Background technology
Tokamak Plasma rupture runs the threat caused to equipment safety, is to hinder magnetic confinement nuclear fusion development
One of key factor, Plasma disruption protection is one of the study hotspot in the current field.As shown in Figure 1, tokamak
Plasma current 1 and poloidal coil 3 (including Centric solenoid modal coil 3A and poloidal coil 3B) constitute transformer device structure, using change
Depressor principle makes plasma current 1 climb to the current value of needs, and using Ohmic heating and auxiliary heating by the way of pair
Plasma is heated, and obtains the high-temperature plasma needed for fusion.Large-scale tokamak device plasma current reaches
Megampere magnitude, plasma temperature reaches 100,000,000 degrees Celsius, and the interior energy and electromagnetic energy of plasma storage reach that 100,000,000 is burnt
Ear magnitude.Plasma disruption is by caused by plasma complex characteristics, showing as plasma current iplasmaRapid decrease
It was zero (as shown in Figure 3).The huge interior energy of plasma and electromagnetic energy can rupture the time of moment, about a few tens of milliseconds
Interior, fast dissipation acts on internal vacuum chamber formation heat deposition in internal vacuum chamber.Energy of plasma is huge, and true
The heat deposition skewness formed on empty room inner part, is easily caused vacuum chamber local because the energy of deposition is excessive and damages.
Because energy of plasma is huge and rupture can not be avoided, how to alleviate rupture transient plasma huge energy pair
The threat of equipment safety is the focus studied at present.For rupture transient plasma energy in internal vacuum chamber formation heat deposition
Inhomogeneities, existing numerous studies explore correlation alleviation method.A large amount of gas injection (Massive Gas
Injection, MGI) it is to study most commonly used rupture alleviation method at present, it mainly injects in rupture moment into vacuum chamber
A large amount of foreign gases, can increase the collision loss of plasma, energy of plasma is equably dissipated in rupture moment
Internal vacuum chamber, prevents from being damaged because the heat deposition that vacuum chamber is locally born is excessive.Other resonant field disturbance (Resonant
Magnetic Perturbations, RMP) can also by suppressing the generation of runaway electron, reduce because runaway electron hit it is true
The local high power heat deposition that empty room inner part is produced.Although MGI and RMP takes on existing most of tokamak devices
Relatively good rupture remission effect was obtained, but these methods can not reduce the total of rupture moment internal vacuum chamber heat deposition
Amount, rupture remission effect is limited.Following large-scale tokamak device energy of plasma is bigger, is more than the 100 of existing apparatus
Times, can existing method alleviate harm that following large-scale plant Plasma disruption huge energy causes also without final conclusion.
The summation that Plasma disruption process is dissipated in internal vacuum chamber energy is bigger, i.e. the heat deposition in vacuum chamber formation
Total amount is bigger, and it is also bigger to rupture the infringement that is caused to device, and existing rupture alleviation method can not reduce rupture moment and be dissipated in
The summation of internal vacuum chamber energy.This just proposes a brand-new problem to researcher in this field, how in rupture wink
Between plasma part energy is exported into vacuum chamber, reduce and be dissipated in the summation of internal vacuum chamber energy, alleviate plasma and break
Split infringement of the huge energy to device.
The content of the invention
Plasma part electromagnetic energy is exported into vacuum using electromagnetic coupled in rupture moment the invention provides one kind
The method and apparatus of room, can reduce rupture moment is dissipated in the summation of internal vacuum chamber energy, reduces internal vacuum chamber heat sink
Product total amount, alleviates infringement of the Plasma disruption huge energy to internal vacuum chamber part.
Proposition method of the present invention is to set the energy transfer coil of one group and plasmon coupling, and coil installation site will
Close proximity to plasma, to improve the degree of coupling of coil and plasma；And outside vacuum chamber set energy absorbing member and
High-speed switch, three is serially connected to form energy transfer loop；Transient plasma electric current rapid decrease is ruptured, in energy transfer
Induced voltage is produced on coil, is turned on while triggering high-speed switch by tokamak central control system, conducts energy transfer
Induced-current, coupled plasma electromagnetic energy are produced in loop, energy transfer coil；This part electromagnetic energy is by being connected on energy
Measure energy absorbing member in commutating circuit, outside vacuum chamber to absorb, so as to realize part plasma electromagnetic energy
Amount is exported from internal vacuum chamber.
In Plasma disruption moment, the rupture action signal that high-speed switch is sent by tokamak central control system is touched
Hair conducting, ON time makes energy transfer stitch quickly devote oneself to work, plasma electromagnetic energy is exported within one millisecond
Vacuum chamber.Trigger switch is not turned on tokamak central control system in the case of rupture is nonevent, and energy transfer coil is not
Work, does not influence on Tokamak experiment.
Energy Transfer Equipment proposed by the present invention, including energy transfer coil, high-speed switch and energy absorbing member, three
It is serially connected composition energy transfer system.
Described energy transfer coil, installation site will be close proximity to plasma, closer to plasma, with plasma
The coefficient of coup of body is higher, and transfer effect is better.Energy transfer coil can be arranged on the top, middle part or bottom of vacuum chamber；
Energy transfer coil can also be the tandem compound of multiple coils, wherein each coil is respectively provided at the top of vacuum chamber, middle part
Or bottom, to improve the coefficient of coup.Energy transfer coil may be mounted at internal vacuum chamber, can also be outside vacuum chamber.Tool
Body scheme is determined according to corresponding tokamak device actual conditions.
Described energy absorbing member, is installed on outside vacuum chamber, be mainly used in energy absorption transfer stitch coupling etc.
Gas ions electromagnetic energy, it is a resistance energy consuming components that can be, but not limited to.In view of consumed energy is larger, resistance energy consuming components one
As form array by multiple high-power resistance connection in series-parallel, its resistance size should match with energy transfer coil.
Described high-speed switch is arranged on outside vacuum chamber, can be by electronic power switch, such as IGCT or IGBT
The array of composition.Electronic power switch ON time is in musec order, and much smaller than the rupture time of a few tens of milliseconds, satisfaction is quickly led
The need for logical.
Vacuum chamber can be equivalent to the coil of a circle and plasmon coupling, and rupture process also can coupled plasma electromagnetism
Energy.For specific tokamak device, what the time constant of vacuum chamber was to determine, its coupled plasma electromagnetic energy size
Also it is to determine.The time constant in energy transfer loop, can be by adjusting energy transfer coil turn and energy absorption portion
Part parameter (being exactly resistance value for resistance energy consuming components), is flexibly selected, and seeks optimal matching scheme, is coupled at most
Plasma electromagnetic energy.
Device derived from Tokamak Plasma electromagnetic energy of the present invention, can be broken as tokamak device
Split a subsystem of protection total system.Internal vacuum chamber heat is being reduced using this method export section plasma electromagnetic energy
While depositing total amount, the heat deposition for making internal vacuum chamber using means of defences such as MGI is uniformly distributed, the two mutual cooperation, can
Preferably to alleviate the harm that Plasma disruption huge energy is caused, the safety of rupture process tokamak device is ensured.
Brief description of the drawings
Fig. 1 is tokamak three dimensional structure diagram.
Fig. 2 is tokamak two-dimensional structure schematic diagram.
Fig. 3 is Tokamak Plasma rupture current waveform schematic diagram.
Fig. 4 is the three dimensional structure diagram added after energy transfer coil in tokamak.
Fig. 5 is the two-dimensional structure schematic diagram added after energy transfer coil in tokamak.
Fig. 6 is the schematic diagram of tokamak electromagnetic energy transfer device.
Fig. 7 is the equivalent circuit schematic of tokamak electromagnetic energy transfer system.
Wherein, 1- plasmas, 2- vacuum chambers, 3- poloidal coils, 4- energy transfer coils, 5- high-speed switches, 6- energy
Measure absorption piece.
Embodiment
Below in conjunction with drawings and Examples, the present invention will be described in further detail.It should be appreciated that described herein
Specific embodiment only to explain the present invention, is not intended to limit the present invention.
Fig. 1 and Fig. 2 are three peacekeeping two-dimensional structure schematic diagrames of tokamak respectively, and 1 is plasma, and 2 be vacuum chamber, 3
It is poloidal coil (including Centric solenoid modal coil 3A and poloidal coil 3B).Fig. 3 is the current wave of Tokamak Plasma rupture
Shape, to moment c plasma current i since moment bplasmaRapid decrease is zero, plasma current i before ruptureplasmaReach
To a megampere level, rupture time about several ms.
Energy transfer coil 4 is arranged on three diverse location embodiment schematic diagrams of internal vacuum chamber, 4A in Fig. 4 and Fig. 5
The coil on vacuum chamber top is mounted in, 4B is mounted in the coil in the middle part of vacuum chamber, and 4C is mounted in the line of vacuum chamber bottom
Circle, access energy absorption loop after three coil series connection.It can essentially be arranged on other according to the characteristics of different tokamak
Diverse location, can also can be able to be Fig. 4 and Fig. 5 three position groupings outside vacuum chamber in internal vacuum chamber,
Can be other different position groupings.
Fig. 6 is the Energy Transfer Equipment structural representation that middle part embodiment is installed only at using energy transfer coil, energy
Amount transfer stitch 4 intercouples with plasma 1, and 5 be high-speed switch, and 6 be energy absorbing member.Fig. 7 is tokamak electromagnetism
The equivalent schematic diagram of energy transfer, plasma 1, energy transfer coil 4 and vacuum chamber 2 constitute three-winding transformer.Energy turns
Being moved back to road also includes high-speed switch 5 and energy absorbing member 6.
High-speed switch 5 can use existing electronic power switch, including IGCT, IGBT etc..Due to energy transfer line
Loop current is likely to be breached tens of kilo-amperes, it is necessary to be used using multiple electronic power switch parallel combinations.Electronic power switch is led
The microsecond of logical time about tens, within one millisecond, meets requirement of the energy transfer system to switch rapidity.
The central control system of tokamak is monitored to rupture, the rupture sent in rupture moment central control system
Action signal, triggering high-speed switch 5 is closed, and energy transfer system is devoted oneself to work.Energy Transfer Equipment proposed by the present invention can be with
A subsystem of protection total system is ruptured as tokamak, receives the action of central control system when rupture will occur
Order is devoted oneself to work.
In the present embodiment, energy absorbing member is resistance energy consuming components.Resistance energy consuming components constitute battle array with resistance connection in series-parallel
Row, are mainly used in consuming a large amount of electromagnetic energies being transferred out of.
As it will be easily appreciated by one skilled in the art that the foregoing is only presently preferred embodiments of the present invention, it is not used to
The limitation present invention, any modification, equivalent and the improvement made within the spirit and principles of the invention etc., it all should include
Within protection scope of the present invention.
Claims (5)
1. a kind of derived rupture alleviation method of Tokamak Plasma rupture electromagnetic energy, it is characterised in that step is as follows：
Step one：The energy transfer coil of one group and plasmon coupling is set, as close to plasma；
Step 2：Outside vacuum chamber, energy absorbing member and high-speed switch are set, both and energy transfer coil are serially connected
Form energy transfer loop；
Step 3：Switch triggering control end is connected to tokamak central control system；When Plasma disruption does not occur,
High-speed switch is off；In Plasma disruption moment, rupture action letter is sent by tokamak central control system
The conducting of number triggering high-speed switch, energy transfer coil coupled plasma electromagnetic energy, and vacuum chamber is exported by energy absorption portion
Part absorbs.
2. realize the Tokamak Plasma electromagnetic energy transfer device of claim 1 methods described, it is characterised in that including
Energy transfer coil, high-speed switch and energy absorbing member, three are serially connected to form energy transfer loop, wherein energy transfer
Coil is arranged on vacuum chamber top, middle part or bottom, and energy absorbing member is located at outside vacuum chamber, the connection of high-speed switch triggering end
To tokamak central control system.
3. Tokamak Plasma electromagnetic energy transfer device according to claim 2, it is characterised in that:Described energy
The coil that transfer stitch is multiple series connection is measured, wherein each coil is respectively provided at the top, middle part or bottom of vacuum chamber.
4. the Energy Transfer Equipment according to Claims 2 or 3, it is characterised in that：Described high-speed switch is power electronics
The switch arrays of switch, such as IGCT or IGBT composition.
5. the Energy Transfer Equipment according to Claims 2 or 3, it is characterised in that：Described energy absorbing member is resistance
Energy consuming components.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510055460.9A CN104637549B (en) | 2015-02-03 | 2015-02-03 | Tokamak Plasma ruptures electromagnetic energy deriving method and device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510055460.9A CN104637549B (en) | 2015-02-03 | 2015-02-03 | Tokamak Plasma ruptures electromagnetic energy deriving method and device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN104637549A CN104637549A (en) | 2015-05-20 |
| CN104637549B true CN104637549B (en) | 2017-07-18 |
Family
ID=53216198
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201510055460.9A Active CN104637549B (en) | 2015-02-03 | 2015-02-03 | Tokamak Plasma ruptures electromagnetic energy deriving method and device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104637549B (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106053979B (en) * | 2016-05-24 | 2019-01-04 | 华中科技大学 | A kind of Tokamak Plasma rupture simulator and analogy method |
| GB201720518D0 (en) * | 2017-12-08 | 2018-01-24 | Tokamak Energy Ltd | Double poloidal field coils |
| CN108172308A (en) * | 2018-01-10 | 2018-06-15 | 成都大学 | The method that plasma inhibition escape electric current is penetrated based on RMP |
| CN108521709B (en) * | 2018-05-23 | 2020-03-17 | 成都大学 | Method for realizing high-current strong electron acceleration based on Tokamak device |
| CN109300553A (en) * | 2018-09-12 | 2019-02-01 | 成都大学 | The runaway electron beam displacement control method shifted based on control of horizontal displacement and magnetic energy |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59158000A (en) * | 1983-02-25 | 1984-09-07 | 株式会社日立製作所 | Plasma controller |
| JPH02293691A (en) * | 1989-05-08 | 1990-12-04 | Hitachi Ltd | Device for protecting nuclear fusion device |
| JPH09197078A (en) * | 1996-01-16 | 1997-07-31 | Hitachi Ltd | Method and device for controlling superconducting coil current in nuclear fusion device |
| CN101640091B (en) * | 2008-07-28 | 2011-06-15 | 北京北方微电子基地设备工艺研究中心有限责任公司 | Inductive coupling coil and plasma processing device adopting same |
| CN103822532B (en) * | 2014-02-26 | 2015-07-01 | 中国科学院等离子体物理研究所 | Multi-lithium-ball-projectile accurate automatic supply system special for plasma fracturing protecting |
-
2015
- 2015-02-03 CN CN201510055460.9A patent/CN104637549B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN104637549A (en) | 2015-05-20 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104637549B (en) | Tokamak Plasma ruptures electromagnetic energy deriving method and device | |
| Schmidt et al. | Protection of the CERN large hadron collider | |
| RU2503159C2 (en) | Apparatus for compressing plasma and method of compressing plasma | |
| Wen et al. | Research on a current commutation drive circuit for hybrid dc circuit breaker and its optimisation design | |
| Neubauer et al. | Design features of the tokamak TEXTOR | |
| Pautasso et al. | Use of impurity pellets to control energy dissipation during disruption | |
| CN104734185B (en) | A kind of Tokamak Plasma energy of rupture processing unit and processing method | |
| Wu et al. | Analysis for magnetic field disturbance of hybrid DC circuit breaker during breaking | |
| Liu et al. | A fast LVDC vacuum hybrid circuit breaker: Dielectric recovery and design consideration | |
| Tang et al. | Design and characterisation of the high‐current DC breaker driven by explosive | |
| Lin et al. | Study on coordination of resistive-type superconducting fault current limiter and DC circuit breaker in HVDC system | |
| CN202888795U (en) | Passive-heating quench protection device for superconducting magnet | |
| CN101414181B (en) | Superconducting magnet quench protection integrated control interface unit | |
| Du et al. | Research and experiment of a current‐limiting HVDC circuit breaker | |
| Gusev et al. | The basics of spherical tokamaks and progress in European research | |
| CN206619558U (en) | A kind of convenient electronic breaker electron plate installed | |
| CN109300553A (en) | The runaway electron beam displacement control method shifted based on control of horizontal displacement and magnetic energy | |
| Raman et al. | Design Considerations for the Implementation of a High-Field-Side Transient CHI System on QUEST | |
| CN102931635A (en) | Passive heating quenching protection device and method aiming at superconducting magnet | |
| Raman et al. | Design details of the transient chi plasma start-up system on NSTX-U | |
| Nagaoka et al. | Ion heating experiments using perpendicular neutral beam injection in the Large Helical Device | |
| CN201388043Y (en) | Superconducting magnet quench protection integrated control interface unit | |
| Tong et al. | Neutron irradiation influence on high-power thyristor device under fusion environment | |
| Xu et al. | Analysis, design, and testing of mechanical switch for the backup protection of switching network unit in fusion device | |
| CN204230887U (en) | A kind of nonlinear resistance type resonance eliminator |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |