JPS632355B2 - - Google Patents
Info
- Publication number
- JPS632355B2 JPS632355B2 JP56012934A JP1293481A JPS632355B2 JP S632355 B2 JPS632355 B2 JP S632355B2 JP 56012934 A JP56012934 A JP 56012934A JP 1293481 A JP1293481 A JP 1293481A JP S632355 B2 JPS632355 B2 JP S632355B2
- Authority
- JP
- Japan
- Prior art keywords
- magnetic field
- field component
- poloidal
- current
- coil
- 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
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
Landscapes
- Plasma Technology (AREA)
Description
〔産業上の利用分野〕
本発明は、トーラス型核融合装置に係り、特
に、垂直磁場成分および四重極磁場成分を発生す
る複数のポロイダルコイル群と、それらポロイダ
ルコイル群の各々に接続された励磁電源とを有す
るトーラス型核融合装置の改良に関する。
〔従来の技術〕
トーラス型核融合装置、特に、トカマク型核融
合装置には、トーラス状プラズマがフープ力によ
り広がるのを押えるとともに、プラズマのポロイ
ダル断面を一定の楕円形状に保持するために、ポ
ロイダル磁場コイルが配置されている。ポロイダ
ル磁場コイルは、垂直磁場成分と四重極磁場成分
を発生させ、垂直磁場成分でプラズマ主半径方向
のプラズマ中心位置を制御し、四重極磁場成分で
プラズマのポロイダル断面の楕円形状を制御す
る。
〔発明が解決しようとする問題点〕
近時、トカマク型核融合装置では、アスペクト
比（プラズマ主半径／プラズマ副半径）を大きく
するために、ポロイダル磁場コイルの占める体積
を小さくできるハイブリツドコイル方式が採用さ
れてきている。ハイブリツドコイル方式は、第１
図に示すように、真空容器１内に所要の磁場を発
生させるトロイダルコイル２とポロイダルコイル
３とを有するトカマク型核融合装置において、ポ
ロイダルコイル３として例えば３ａ，３ｂ，……
…，３ｅのように形状の異なる複数のコイルを用
い、その各々のコイルに励磁電流を流す励磁電源
を設けたものである。プラズマの位置形状を制御
するのに必要な垂直磁場と四重極磁場を形成する
には、各コイル３ａ，３ｂ，………，３ｅが発生
させる磁場の合成磁場が所要の垂直磁場成分及び
四重極磁場成分をもつように、各コイルに流れる
励磁電流I1，I2，………，I5を各電源により調整
する。しかし、プラズマの位置及び形状が最適な
状態になるように各コイルの磁場を調整すること
は、非常に困難であつた。
プラズマの中心位置及び楕円形状を制御するた
めに必要な垂直磁場と四重極磁場を発生させるコ
イルは、第１図の例では５個のみを示してある
が、一般には数個から数10個のコイルがあるの
で、各コイルを励磁する電流値には各々の組み合
せを採用できる。従つて磁場条件だけに着目し
て、ポロイダルコイル群の各々に適当な電流を流
すと、消費電力が大きくなつてしまう場合も生じ
ていた。実際には、各コイルに流し得る電流値に
は電源容量からの制限により上限、下限値が存在
する。従つて、所要の磁場を得るために各コイル
に流す電流の調整が一層難しくなるという問題が
あつた。
本発明の目的は、プラズマの位置及び形状を計
測してプラズマが最適な状態になるようにポロイ
ダルコイル群に電流を流し、何れかのコイル電流
が制限値に達しても他のコイル電流によつて所要
の磁場が得られ、しかも、コイル群全体の消費電
力が最小となるようなフイードバツク制御系を有
するトーラス型核融合装置を提供することであ
る。
〔問題点を解決するための手段〕
本発明は、上記目的を達成するために、垂直磁
場成分および四重極磁場成分を演算する制御演算
部の演算結果に基づき、ポロイダルコイル群に流
れる電流の消費電力の総和を最小とし各励磁電源
の電流制御値内に収まる各ポロイダルコイル電流
の組合せを演算する電流変換部を備えたトーラス
型核融合装置を提案するものである。
〔作用〕
本発明においては、制御演算部で得られた垂直
磁場成分および四重極磁場成分を発生させる電流
を単純に各ポロイダルコイルに割り振るのでな
く、各励磁電源の容量と消費電力の総和とを同時
に考慮して、各ポロイダルコイル電流の組合せを
求めるので、特定の電源に過大な負荷がかかるこ
とがない。その際に、全体の消費電力が最小とな
り、効率的運転を実行できる。
〔実施例〕
次に、第２図を参照して、本発明の一実施例を
説明する。第２図は、本発明によるプラズマの位
置及び形状のフイードバツク制御系の構成の一例
を示すブロツク図である。
トカマク型核融合装置のプラズマ４の位置及び
形状（Rp、δ）は、電磁プローブを有する計測
器５により計測される。すなわち、計測器５は、
プラズマ電流から発生する磁力線の電磁誘導の結
果生ずる電流を検出し、制御演算部６に入力す
る。
制御演算部６ではPID（比例、積分、微分）制
御演算により、Rp、δを予め設定された目標値
Rpo、δoに制御するために必要な垂直磁場Bvと
四重極磁場Bqを計算する。このPID制御演算は
次式により行われる。
Bv＝Kpv（Rp−Rpo）＋KIV∫t p（Rp−Rpo）dt＋KDVd
Rp／dt……(1)
Bq＝Kpq（δ−δo）＋KIq∫t p（δ−δo）dt＋KDｑ
dδ／dt……(2)
ただし、Kpv、………、KDｑはフイードバツ
クゲイン定数であり、サフイツクスＰ、Ｉ、Ｄは
それぞれ比例、積分、微分を表わし、サフイツク
スｖ、ｑはそれぞれ垂直磁場、四重極磁場を表し
ている。
制御演算部６が式(1)、(2)により計算したBv、
Bqは、電流値変換部７に入力され、消費電力を
最小にするように各コイル３ａ，３ｂ，………，
３ｅに流すべき電流I1，I2，………，I5を決定す
る。これらの制御電流指令値I1，I2，………，I5
は、ポロイダル電源８に入力され、プラズマ４に
対する垂直磁場Bvと四重極磁場Bqを発生させ、
プラズマ４が最適状態になるように制御する。次
に、電流値変換部７の電流値演算の手順について
述べる。一般に、コイル３ａ，３ｂ，………，３
ｅに任意の電流I1，I2，………，I5を流すと、プ
ラズマ領域には、磁場の５次までのフーリエ成
分、すなわちBo（一様成分）、Bv（垂直成分）、Bq
（四重極成分）、B6（六重極成分）、B8（八重極成
分）の合成磁場が形成される。この関係は行列式
を用いると、次式で表される。
ここでβ＝〔βij〕は、コイルの幾何学的寸法で
決まる定数である。
従つて、(3)式を解くと、磁場のフーリエ成分Ｂ
を与えたときに各コイルに流すべき電流Ｉは次式
から得られる。
Ｉ＝Ｈ・Ｂ ……(4)
ただし、Ｉ＝（I1、………、I5）T、Ｂ＝（Bv、
Bq、B0、B6、B8）T、Ｈ＝β-1であり、Ｔは転置
行列、−１は逆行列を表わす。
コイル電流I1，I2，………，I5のうち、ｌ個の
コイル電流が制限値に達している場合に、(4)式を
用いてコイルに流す消費電力を最小にする電流値
を求めることは、このとき所要の垂直磁場Bvと
四重極磁場Bqを作り出し、しかもコイルの消費
電力Ｐ＝R1I1 2＋………＋R5I5 2（ただし、R1、…
……、R5は各コイルの抵抗値とする。）を最小に
する電流値を求める問題に帰着する。この消費電
力Ｐは、例えばラグランジユの未定乗数法を用い
て、次のように求められる。
制限値に達している電流をIl＝（IlA………、
Ill）、制限値に達していない電流をIh＝（IhA……
…Ih(5-l)）（ただし、コイルの個数はｌ＋ｈ＝５の
場合である。）と表せば、(4)式を用いて、
[Industrial Application Field] The present invention relates to a torus-type nuclear fusion device, and particularly relates to a plurality of poloidal coil groups that generate vertical magnetic field components and quadrupole magnetic field components, and an excitation power source connected to each of the poloidal coil groups. The present invention relates to an improvement of a torus-type nuclear fusion device having the following. [Prior Art] Torus-type fusion devices, especially tokamak-type fusion devices, use poloidal fusion devices to suppress the spread of torus-shaped plasma due to hoop force and to maintain the poloidal cross section of the plasma in a constant elliptical shape. A magnetic field coil is arranged. The poloidal magnetic field coil generates a vertical magnetic field component and a quadrupole magnetic field component, the vertical magnetic field component controls the plasma center position in the main radial direction of the plasma, and the quadrupole magnetic field component controls the elliptical shape of the poloidal cross section of the plasma. . [Problems to be solved by the invention] Recently, in tokamak type nuclear fusion devices, in order to increase the aspect ratio (plasma major radius/plasma minor radius), a hybrid coil system that can reduce the volume occupied by the poloidal magnetic field coil has been developed. It is being adopted. The hybrid coil method is the first
As shown in the figure, in a tokamak-type nuclear fusion device having a toroidal coil 2 and a poloidal coil 3 that generate a required magnetic field in a vacuum vessel 1, the poloidal coils 3 are, for example, 3a, 3b, . . .
. . , 3e, a plurality of coils having different shapes are used, and an excitation power source is provided to supply an excitation current to each coil. In order to form the vertical magnetic field and quadrupole magnetic field necessary to control the position and shape of the plasma, the composite magnetic field of the magnetic fields generated by each coil 3a, 3b, ......, 3e has the required vertical magnetic field component and quadrupole magnetic field. The excitation currents I 1 , I 2 , . . . , I 5 flowing through each coil are adjusted by each power source so as to have a heavy pole magnetic field component. However, it is extremely difficult to adjust the magnetic field of each coil so that the position and shape of the plasma are optimal. The example in Figure 1 shows only five coils that generate the vertical magnetic field and quadrupole magnetic field necessary to control the center position and elliptical shape of the plasma, but in general there are several to several dozen coils. Since there are coils, each combination can be adopted for the current value to excite each coil. Therefore, if an appropriate current is passed through each of the poloidal coil groups by focusing only on the magnetic field conditions, power consumption may increase. In reality, there are upper and lower limits to the current value that can flow through each coil due to limitations from the power supply capacity. Therefore, there was a problem in that it became more difficult to adjust the current flowing through each coil in order to obtain the required magnetic field. The purpose of the present invention is to measure the position and shape of the plasma and flow current through a group of poloidal coils so that the plasma is in an optimal state. It is an object of the present invention to provide a torus-type nuclear fusion device having a feedback control system capable of obtaining a required magnetic field and minimizing power consumption of the entire coil group. [Means for Solving the Problems] In order to achieve the above object, the present invention reduces the consumption of current flowing through the poloidal coil group based on the calculation results of the control calculation unit that calculates the vertical magnetic field component and the quadrupole magnetic field component. This paper proposes a torus-type fusion device equipped with a current converter that minimizes the total power and calculates a combination of poloidal coil currents that falls within the current control value of each excitation power source. [Operation] In the present invention, the current for generating the vertical magnetic field component and the quadrupole magnetic field component obtained by the control calculation unit is not simply allocated to each poloidal coil, but the capacity of each excitation power source and the sum of power consumption are Since the combination of each poloidal coil current is determined at the same time, an excessive load is not placed on a specific power source. At this time, the overall power consumption is minimized and efficient operation can be performed. [Embodiment] Next, an embodiment of the present invention will be described with reference to FIG. FIG. 2 is a block diagram showing an example of the configuration of a feedback control system for plasma position and shape according to the present invention. The position and shape (Rp, δ) of the plasma 4 of the tokamak type nuclear fusion device are measured by a measuring instrument 5 having an electromagnetic probe. That is, the measuring instrument 5 is
A current generated as a result of electromagnetic induction of magnetic lines of force generated from the plasma current is detected and input to the control calculation unit 6. The control calculation unit 6 uses PID (proportional, integral, differential) control calculation to set Rp and δ to preset target values.
Calculate the vertical magnetic field Bv and quadrupole magnetic field Bq required to control Rpo and δo. This PID control calculation is performed using the following equation. Bv=Kpv(Rp−Rpo)+K IV ∫ t p (Rp−Rpo)dt+K DV d
Rp／dt……(1) Bq＝Kpq(δ−δo)＋K I q∫ t p (δ−δo)dt＋K D q
dδ/dt...(2) However, Kpv,......, K D q are feedback gain constants, suffixes P, I, and D represent proportional, integral, and differential, respectively, and suffixes v and q are respectively It represents a vertical magnetic field and a quadrupole magnetic field. Bv calculated by the control calculation unit 6 using equations (1) and (2),
Bq is input to the current value converter 7, and is applied to each coil 3a, 3b,..., so as to minimize power consumption.
Determine the currents I 1 , I 2 , . . . , I 5 to be passed through 3e. These control current command values I 1 , I 2 , ......, I 5
is input to the poloidal power supply 8, which generates a vertical magnetic field Bv and a quadrupole magnetic field Bq for the plasma 4,
The plasma 4 is controlled to be in an optimal state. Next, the procedure of current value calculation by the current value converter 7 will be described. Generally, the coils 3a, 3b, ......, 3
When arbitrary currents I 1 , I 2 , ......, I 5 are passed through e, the plasma region contains Fourier components up to the fifth order of the magnetic field, namely Bo (uniform component), Bv (vertical component), Bq
A composite magnetic field of (quadrupole component), B 6 (hexapole component), and B 8 (octupole component) is formed. This relationship is expressed by the following equation using a determinant. Here, β=[βij] is a constant determined by the geometric dimensions of the coil. Therefore, by solving equation (3), we get the Fourier component B of the magnetic field.
The current I to be passed through each coil when given is obtained from the following equation. I=H・B...(4) However, I=(I 1 ,......, I 5 ) T , B=(Bv,
Bq, B 0 , B 6 , B 8 ) T , H=β −1 , where T represents a transposed matrix and −1 represents an inverse matrix. When l coil currents among the coil currents I 1 , I 2 , ......, I 5 have reached the limit value, the current value that minimizes the power consumption flowing through the coil using equation (4) In order to obtain the required vertical magnetic field Bv and quadrupole magnetic field Bq, the power consumption of the coil P = R 1 I 1 2 + + R 5 I 5 2 (However, R 1 ,...
..., R 5 is the resistance value of each coil. ) is reduced to the problem of finding the current value that minimizes. This power consumption P is determined as follows using, for example, Lagrange's undetermined multiplier method. The current that has reached the limit value is Il = (Il A ......,
Ill), the current that has not reached the limit value is Ih = (Ih A ...
...Ih (5-l) ) (However, the number of coils is l + h = 5.) Using equation (4),
【式】【formula】
本発明によれば、トーラス型核融合装置、特に
トカマス型核融合装置において、プラズマの位置
及び形状を計測してフイードバツク制御し、プラ
ズマの状態を最適にするとともに、励磁電源に制
限値があつても、電源の消費電力を最小にして、
プラズマの位置及び形状を制御するのに必要な垂
直磁場及び四重極磁場をポロイダルコイル群に発
生させることができる。
According to the present invention, in a torus-type fusion device, especially a torus-type fusion device, the position and shape of plasma are measured and feedback controlled to optimize the plasma state, and the excitation power source has a limit value. Also, the power consumption of the power supply is minimized,
The poloidal coils can generate the vertical and quadrupole magnetic fields necessary to control the position and shape of the plasma.
第１図はハイブリツドコイル方式のトーラス型
核融合装置の上半分のポロイダル断面図、第２図
は本発明によるプラズマの位置及び形状のフイー
ドバツク制御系の構成を示すブロツク図である。
３ａ〜３ｅ……ハイブリツドコイル、４……プ
ラズマ、５……計測器、６……制御演算部、７…
…電流値変換部、８……ポロイダルコイル励磁電
源。
FIG. 1 is a poloidal cross-sectional view of the upper half of a hybrid coil type torus-type fusion device, and FIG. 2 is a block diagram showing the configuration of a feedback control system for plasma position and shape according to the present invention. 3a to 3e...hybrid coil, 4...plasma, 5...measuring instrument, 6...control calculation section, 7...
...Current value converter, 8... Poloidal coil excitation power supply.
Claims (1)
るポロイダルコイル群と、前記ポロイダルコイル
群の各々に接続された励磁電源と、ポロイダル断
面におけるプラズマ水平方向位置および楕円変形
度を検出する検出器と、前記検出器で得た計測値
を予め定めた目標値に制御するための前記垂直磁
場成分および四重極磁場成分を演算する制御演算
部と、演算された垂直磁場成分および四重極磁場
成分を発生させるために前記ポロイダルコイル群
の各々に流すべき電流を演算する電流変換部とを
備えたトーラス型核融合装置において、 前記電流変換部が、 前記ポロイダルコイル群に流れる電流の消費電
力の総和を最小とし前記各励磁電源の電流制限値
内に収まる各ポロイダルコイル電流の組合せを演
算する手段からなることを特徴とするトーラス型
核融合装置。[Claims] 1. A poloidal coil group that generates a vertical magnetic field component and a quadrupole magnetic field component, an excitation power source connected to each of the poloidal coil groups, and a plasma horizontal position and elliptic deformation degree in a poloidal cross section that are detected. a detector, a control calculation unit that calculates the vertical magnetic field component and quadrupole magnetic field component for controlling the measured value obtained by the detector to a predetermined target value, and a control calculation unit that calculates the vertical magnetic field component and quadrupole magnetic field component, and A torus-type nuclear fusion device comprising: a current converter that calculates a current to be passed through each of the poloidal coil groups in order to generate a polar magnetic field component, wherein the current converter calculates the power consumption of the current flowing through the poloidal coil group A torus-type nuclear fusion device comprising means for calculating a combination of poloidal coil currents that minimizes the sum and falls within a current limit value of each excitation power source.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56012934A JPS57128500A (en) | 1981-02-02 | 1981-02-02 | Toroidal nuclear fusion reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56012934A JPS57128500A (en) | 1981-02-02 | 1981-02-02 | Toroidal nuclear fusion reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57128500A JPS57128500A (en) | 1982-08-10 |
| JPS632355B2 true JPS632355B2 (en) | 1988-01-18 |
Family
ID=11819112
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56012934A Granted JPS57128500A (en) | 1981-02-02 | 1981-02-02 | Toroidal nuclear fusion reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57128500A (en) |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5442597A (en) * | 1977-09-09 | 1979-04-04 | Hitachi Ltd | Nuclear fusion device |
-
1981
- 1981-02-02 JP JP56012934A patent/JPS57128500A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57128500A (en) | 1982-08-10 |
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