CN100367413C - Method and device for measuring corona current in Tokamak device - Google Patents
Method and device for measuring corona current in Tokamak device Download PDFInfo
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- CN100367413C CN100367413C CNB2005100377140A CN200510037714A CN100367413C CN 100367413 C CN100367413 C CN 100367413C CN B2005100377140 A CNB2005100377140 A CN B2005100377140A CN 200510037714 A CN200510037714 A CN 200510037714A CN 100367413 C CN100367413 C CN 100367413C
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Abstract
The present invention discloses a method and a device for measuring corona current in a Tokamak device. Mutually paralleled screw coils with high frequency response are arranged on the inner wall of a vacuum chamber of the Tokamak device, and the situation of the variation of a magnetic field in the vacuum chamber can be obtained by measuring induction current on the screw coils. On the basis, the present invention can carry out measurement according to a high-temperature plasma, peripherical longitudinal field magnet, pole direction field magnet and the vacuum chamber body through the screw coils arranged in the vacuum chamber of the Tokamak device, and in this way, the present invention not only can obtain the value of corona current, but also can obtain the annularly distributed inhomogeneity of the corona current along the device.
Description
Technical field
The present invention relates to fusionplasma and electronic applications, the measuring method and the device of corona current in a kind of specifically tokamak device.
Background technology
Deepening continuously and develop along with the fusionplasma physical study, research for tokamak device, people begin to pursue more the Q factor and the restraint performance of its plasma, and try to explore some and relevant engineering and the physical problem of the advanced tokamak fusion reactor of following stable state, elongating the research of plasma position shape from conventional circular section plasma position shape research steering superconduction on-circular cross-section is the main direction of Tokamak nuclear fusion device development in recent years.Tokamak device with plasma elongation cross section helps improving plasma parameter, specific pressure value β particularly, and the size of β value directly with future fusion reactor economic quality relevant, the β value is high more, the economic efficacy of device is good more, and therefore the position shape of modern tokamak device ionic medium body is generally all adopted and elongated the cross section.Yet elongate the but very easy perpendicular displacement incident of bringing out plasma in cross section, in case because certain disturbance or system are out of control, its confined equilibrium is broken, plasma will the collapse of energy of plasma quencher and electric current occur up or down at random vertically towards X-POINT place rapid movement thereupon.In this transients, will produce a kind of corona current is that the scraping layer of corona current (utmost point in its mobile field swooning when section configuration is similar to lunar eclipse) outside the inc outermost layer magnetic surface of the magnetic line of force enters divertor target plate or vacuum chamber shell wall through the X-POINT both sides, forms the closed-loop path.Because the randomness that this electric current produces is bigger, it is asymmetric to distribute along big ring direction, and action time is short, so very big to the harmfulness of device.Not only can make parts generation local overheating even ablations such as limiter, antenna, divertor, target plate or cushion block close with plasma or that directly contact, respond to local eddy currents but also can be coupling on the plasma metal parts on every side by magnetic field, produce huge transient electromagnetic load, cause vacuum chamber and support system thereof to bear the huge impact effect.For superconducting Tokamak sizable superpotential of also might in the poloidal field magnet, inducting, finally cause the conductor quench.This harmfulness of corona current to device, be in the Physical Experiment of some big-and-middle-sized tokamak devices, to find the earliest, as finding that on the JET device graphite tile comes off and the trapped orbit distortion, on devices such as Alcator C-MOD and JT-60, find to face the local deformation of the bending of plasma first wall parts set bolt, tile breakage and vacuum chamber housing.Therefore for building following tokamak fusion reactor, corona current is one of unavoidable focal issue, and the research of this work is of great significance.
In the world because very late to the research starting of HALO electric current, after the third generation tokamak such as JT-60 of European JET device, Japan put into operation, device constantly is subjected to serious perpendicular displacement incident and impacts, and the research of break physics and HALO electric current is just paid attention to by people day by day.ITER (international thermonuclear fusion heap) entered project engineering stage afterwards, and the research of HALO electric current just is listed in R﹠amp; The urgent research topic of D.On devices such as JET, also carrying out some experimental measurement methods at present, studying the HALO electric current in the world still relies on the experiment service data of phase peri position shape device inductive statistics in addition the basic skills of tokamak device, suppose that plasma is for being symmetrically distributed, then by TSC, tokamak such as EFIT discharge simulator program carries out two Dimensional Simulation of Air Motion, the defective of this method maximum is to be difficult to the asymmetry rule that simulation HALO electric current distributes along big ring direction, thereby can't obtain the three dimensions field distribution of HALO electric current, and for tokamak device, the inhomogeneous electromagnetism load that this asymmetry hoop distributed current causes is one of design the most dangerous operating mode that the time must take in, and it has great destructiveness to apparatus structure.
Summary of the invention
This patent is exactly the angle of building fusion reactor from future, the utilization experimental measurement method, measure at tokamak device internal vacuum chamber layout rib collar coil, not only can obtain the size of HALO electric current, and can obtain the HALO electric current along the unevenness of device ring to distribution.
Technical scheme
The measuring method of HALO electric current in the tokamak device, it is characterized in that: on tokamak device vacuum chamber inwall, arrange the rib collar coil with high frequency response parallel with one another, when tokamak device internal vacuum chamber plasma generation vertical instability, rib collar coil with high frequency response produces voltage signal, by integrator loop the voltage signal from the rib collar coil is carried out filtering amplification and Signal Separation, be varied to current signal as calculated the machine data acquisition module carry out data acquisition and the storage, the data of gathering are delivered to computing machine, by measuring the induction current on the rib collar coil, can obtain the situation of change in internal vacuum chamber magnetic field, on this basis according to high-temperature plasma in the tokamak device, vertical on every side field magnet, poloidal field magnet and vacuum chamber body comprise the inductance coefficent of internal part and the current value on each rib collar coil, when calculating owing to plasma generation vertical instability, in each diverse location of internal vacuum chamber HALO size of current, and then the overall process that can also subtract in internal vacuum chamber fast moving and rate by the commercial visualization procedure inverting of existing computing machine plasma, the HALO electric current color cloud picture that produces when obtaining plasma generation vertical instability.
The measurement mechanism of HALO electric current in the tokamak device, comprise Computer Processing center, integrator, rib collar coil, it is characterized in that: will on tokamak device vacuum chamber inwall, be furnished with rib collar coil in parallel, the voltage signal output end of rib collar coil connects integrator loop voltage signal input end, the integrator loop current signal output end connects the signals collecting end of computer data acquisition system, and the computer data acquisition system data output end connects Computer Processing centre data input end.
The described high frequency response rib collar coil response time is 2E-4s.
The rib collar coil of arranging on the described tokamak device vacuum chamber inwall is to arrange to the cross section according to the utmost point of the big ring direction of vacuum chamber, at least arrange two at each utmost point to the sectional position, spend symmetric offset spread along the every interval 22.5 of big ring direction circumference along the rib collar coil that the utmost point is arranged to the cross section.
The described utmost point is furnished with two rib collar coils to the cross section, lays respectively at bottom and the top of the utmost point to the cross section.
Inventive principle
Performance parameter during according to plasma generation vertical instability is (when in a single day instability takes place in plasma, meeting is moved rapidly and rate subtracts, its speed reaches 50 meter per seconds), development high frequency response rib collar coil (the resonant time is 2E-4s), make its changes of magnetic field can article on plasma body generation perpendicular displacement incident the time make transient response, the generation momentary current changes, and measuring accuracy is not more than 0.3%.The tokamak device internal vacuum chamber is together in parallel to the rib collar coil of arranging one by one along the hoop and the utmost point, by integrator loop the current signal from the rib collar coil is carried out filtering amplification and Signal Separation then, and machine data acquisition system as calculated, whole measurement data are delivered to the Computer Processing center, by measuring the induction current on the rib collar coil, can obtain the situation of change in internal vacuum chamber magnetic field.On this basis according to high-temperature plasma in the tokamak device, vertical field magnet, poloidal field magnet and vacuum chamber body comprise the inductance coefficent of internal part and the current value on each rib collar coil on every side, when calculating owing to plasma generation vertical instability, in each diverse location of internal vacuum chamber HALO size of current, and then the overall process that can also subtract in internal vacuum chamber fast moving and rate by the commercial visualization procedure inverting of existing computing machine plasma, the HALO electric current color cloud picture that produces when obtaining plasma generation vertical instability.
The invention effect
Measure at tokamak device internal vacuum chamber layout rib collar coil, not only can obtain the size of HALO electric current, and can obtain the HALO electric current along the unevenness of device ring to distribution.
Description of drawings
Fig. 1 is that rib collar coil of the present invention is arranged synoptic diagram at tokamak device vacuum chamber inwall along big ring direction.
Fig. 2 rib collar coil of the present invention at tokamak device vacuum chamber inwall along the layout synoptic diagram of the utmost point to the cross section.
Fig. 3 rib collar loop construction of the present invention synoptic diagram.
Fig. 4 HALO current measurement of the present invention quad lines line structure synoptic diagram.
Embodiment
Referring to Fig. 1～4.
The measurement mechanism of HALO electric current in the tokamak device, comprise Computer Processing center, integrator, rib collar coil, the rib collar coil is to arrange (see figure 1) according to the utmost point of the big ring direction of vacuum chamber to the cross section, spends symmetric offset spread along the rib collar coil that the utmost point is arranged to cross section (being also referred to as little ring direction) along the every interval 22.5 of big ring direction circumference.Arrange a rib collar coil at each utmost point respectively to the top and the bottom position in cross section.The rib collar coil can be arranged arbitrarily at the vacuum chamber inwall, its objective is for electric current, and then derive each position HALO electric current in the tokamak device, should say by this place's rib collar coil of measurement, as long as the vacuum chamber inner wall position allows, the rib collar coil configuration is The more the better.Fig. 2 is illustrated in a utmost point and has arranged five rib collar coils on cross section (along little ring direction).
Each rib collar coil is parallel with one another, the voltage signal output end of rib collar coil connects integrator loop voltage signal input end, the integrator loop current signal output end connects the signals collecting end of computer data acquisition system, and the computer data acquisition system data output end connects Computer Processing centre data input end.
By measuring the induction current on the rib collar coil, can obtain the situation of change in internal vacuum chamber magnetic field, on this basis according to high-temperature plasma in the tokamak device, vertical on every side field magnet, poloidal field magnet and vacuum chamber body comprise the inductance coefficent of internal part and the current value on each rib collar coil, when calculating owing to plasma generation vertical instability, in each diverse location of internal vacuum chamber HALO size of current, and then the overall process that can also subtract in internal vacuum chamber fast moving and rate by the commercial visualization procedure inverting of existing computing machine plasma, the HALO electric current color cloud picture that produces when obtaining plasma generation vertical instability.
The concrete parameter of selected rib collar coil: port voltage changes dI/dt ~ 1KA/ms, considers that the response frequency of the influence of peripheral metal eddy current is 25KHz, 4 layers of the coiling numbers of plies, staggered area NS/1 ~ 0.87m
2/ m, S/N ratio is: 10, winding enamel paint linear diameter 0.5mm, pitch is 1.25mm, size: long 5cm, high 2.8cm, thick 0.7cm.
Claims (4)
1. the measuring method of HALO electric current in the tokamak device, it is characterized in that: on tokamak device vacuum chamber inwall, arrange the rib collar coil with high frequency response parallel with one another, when tokamak device internal vacuum chamber plasma generation vertical instability, rib collar coil with high frequency response produces voltage signal, by integrator loop the voltage signal from the rib collar coil is carried out filtering amplification and Signal Separation, be varied to current signal as calculated the machine data acquisition module carry out data acquisition and the storage, the data of gathering are delivered to computing machine, by measuring the induction current on the rib collar coil, can obtain the situation of change in internal vacuum chamber magnetic field, on this basis according to high-temperature plasma in the tokamak device, vertical on every side field magnet, poloidal field magnet and vacuum chamber body comprise the inductance coefficent of internal part and the current value on each rib collar coil, when calculating owing to plasma generation vertical instability, in each diverse location of internal vacuum chamber HALO size of current, and then the overall process that can also subtract in internal vacuum chamber fast moving and rate by the commercial visualization procedure inverting of existing computing machine plasma, the HALO electric current color cloud picture that produces when obtaining plasma generation vertical instability.
2. the measurement mechanism of HALO electric current in the tokamak device, comprise Computer Processing center, integrator, rib collar coil, it is characterized in that: will on tokamak device vacuum chamber inwall, be furnished with rib collar coil in parallel, the voltage signal output end of rib collar coil connects integrator loop voltage signal input end, the integrator loop current signal output end connects the signals collecting end of computer data acquisition system, and the computer data acquisition system data output end connects Computer Processing centre data input end.
3. the measuring method of HALO electric current in the tokamak device according to claim 1 is characterized in that the described high frequency response rib collar coil response time is 2E-4s.
4. the measurement mechanism of HALO electric current in the tokamak device according to claim 2, it is characterized in that described rib collar coil is to arrange to the cross section according to the utmost point of the big ring direction of vacuum chamber, at least arrange two at each utmost point to the sectional position, spend symmetric offset spread along the every interval 22.5 of big ring direction circumference along the rib collar coil that the utmost point is arranged to the cross section.
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| Application Number | Priority Date | Filing Date | Title |
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| CNB2005100377140A CN100367413C (en) | 2005-01-27 | 2005-01-27 | Method and device for measuring corona current in Tokamak device |
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| CNB2005100377140A CN100367413C (en) | 2005-01-27 | 2005-01-27 | Method and device for measuring corona current in Tokamak device |
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| CN1731914A CN1731914A (en) | 2006-02-08 |
| CN100367413C true CN100367413C (en) | 2008-02-06 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN100430739C (en) * | 2006-10-18 | 2008-11-05 | 中国科学院等离子体物理研究所 | Apparatus for measuring entrance phase position of Tokamak low-noise-wave antenna array and phase-appraising method |
| CN101488372B (en) * | 2009-01-22 | 2013-01-09 | 中国科学院等离子体物理研究所 | Hardware compensating apparatus for plasma current |
| CN102878917B (en) * | 2012-09-17 | 2014-11-12 | 华中科技大学 | Signal operation device based on Rogowski coil measurement |
| CN107020474B (en) * | 2016-02-01 | 2019-03-26 | 西安核设备有限公司 | A kind of whole cyclic tooling of large size double-layer thin wall D type section vacuum chamber and process |
| GB201720518D0 (en) * | 2017-12-08 | 2018-01-24 | Tokamak Energy Ltd | Double poloidal field coils |
| CN113186516A (en) * | 2021-04-01 | 2021-07-30 | 上海征世科技股份有限公司 | Cooling system for substrate table of MPCVD equipment |
| CN113593726B (en) * | 2021-08-06 | 2023-12-08 | 核工业西南物理研究院 | Method and device for controlling edge local mode |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| SU1153698A1 (en) * | 1983-12-23 | 1985-10-07 | Yu V Gribov | Device for stabilizing equilibrum position of plasma filament in tokamak |
| CN1112710C (en) * | 1996-10-17 | 2003-06-25 | 中国科学院等离子体物理研究所 | Electric field drifting electron injection method and device for increasing fusion plasma restraint performance |
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Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| SU1153698A1 (en) * | 1983-12-23 | 1985-10-07 | Yu V Gribov | Device for stabilizing equilibrum position of plasma filament in tokamak |
| CN1112710C (en) * | 1996-10-17 | 2003-06-25 | 中国科学院等离子体物理研究所 | Electric field drifting electron injection method and device for increasing fusion plasma restraint performance |
Non-Patent Citations (1)
| Title |
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| EAST核聚变实验装置中极向场线圈电流的确定. 王华忠，罗家融.原子能科学技术，第40卷第3期. 2006 * |
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