JPS6122919B2 - - Google Patents

Info

Publication number
JPS6122919B2
JPS6122919B2 JP54105870A JP10587079A JPS6122919B2 JP S6122919 B2 JPS6122919 B2 JP S6122919B2 JP 54105870 A JP54105870 A JP 54105870A JP 10587079 A JP10587079 A JP 10587079A JP S6122919 B2 JPS6122919 B2 JP S6122919B2
Authority
JP
Japan
Prior art keywords
current transformer
air
core current
transformer coil
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
Application number
JP54105870A
Other languages
Japanese (ja)
Other versions
JPS5630679A (en
Inventor
Hiroshige Watanabe
Shohei Suzuki
Yoshiaki Kazawa
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP10587079A priority Critical patent/JPS5630679A/en
Publication of JPS5630679A publication Critical patent/JPS5630679A/en
Publication of JPS6122919B2 publication Critical patent/JPS6122919B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors

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  • Plasma Technology (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は核融合装置に係り、特にトーラス型核
融合装置のコイルの配列に関するものである。
DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to a nuclear fusion device, and particularly to a coil arrangement of a torus-type nuclear fusion device.

〔従来の技術〕[Conventional technology]

従来、トーラス型核融合装置の多くは、プラズ
マの加熱又は保持のために、プラズマと鎖交する
変化磁束を必要とする。この変化磁束を作る方法
は、大別して、鉄心変流器コイルを用いる方法と
空心変流器コイルを用いる方法とに分けられる。
最近の大型装置では、磁気飽和が無いという利点
から、空心変流器コイルを用いる方法が多用され
ている。
Conventionally, many torus-type fusion devices require a changing magnetic flux that interlinks with the plasma in order to heat or maintain the plasma. Methods for creating this varying magnetic flux can be roughly divided into methods using iron-core current transformer coils and methods using air-core current transformer coils.
In recent large-scale devices, methods using air-core current transformer coils are often used because of the advantage of no magnetic saturation.

〔発明が解決しようとする問題点〕[Problem that the invention seeks to solve]

空心変流器コイルの使用上最も問題となるの
は、導電性材料を用いた構造物が変化磁束の中に
存在すると渦電流を生じ、この渦電流による不整
磁場がプラズマ閉じ込め磁場に悪影響を及ぼし、
遂にはプラズマが消減してしまう事態が発生する
ことである。
The biggest problem when using air-core current transformer coils is that when a structure made of conductive material exists in a changing magnetic flux, eddy currents are generated, and the irregular magnetic field caused by these eddy currents has a negative effect on the plasma confinement magnetic field. ,
Eventually, a situation will occur where the plasma will disappear.

従来のトーラス型核融合装置の概要を示す第3
図により、それを説明する。図において、円環状
の真空容器10は内部にプラズマ12を発生させ
るものである。この真空容器10の小周(ポロイ
ダル)方向にはトロイダルコイル14が配置さ
れ、真空容器10のトーラス方向には空心変流器
コイル16と垂直磁場コイル18がそれぞれ配置
されている。真空容器10及びその周囲に配置さ
れるコイル14,16,18は上下のベース2
0,22に支持されている。
Part 3 shows an overview of the conventional torus-type fusion device.
This will be explained using diagrams. In the figure, an annular vacuum vessel 10 generates plasma 12 inside. A toroidal coil 14 is arranged in the poloidal direction of the vacuum vessel 10, and an air-core current transformer coil 16 and a vertical magnetic field coil 18 are arranged in the torus direction of the vacuum vessel 10, respectively. The vacuum container 10 and the coils 14, 16, 18 arranged around it are connected to the upper and lower bases 2.
It is supported by 0.22.

このような構成のトーラス型核融合装置では、
トロイダルコイル14の垂直磁場コイル18の作
る磁場によりプラズマ12を真空容器10内に閉
じ込め、更に空心変流器コイル16が作る磁束Φ
を急激に変化させてプラズマ12に電流を流し、
プラズマ12の閉じ込め及び加熱を行なう。
In a torus-type fusion device with this configuration,
The plasma 12 is confined within the vacuum vessel 10 by the magnetic field created by the vertical magnetic field coil 18 of the toroidal coil 14, and the magnetic flux Φ created by the air-core current transformer coil 16 is
A current is applied to the plasma 12 by rapidly changing the
The plasma 12 is confined and heated.

ところが、従来のトーラス型核融合装置では、
ベース20,22が空心変流器コイル16の磁束
Φと鎖交しているため磁束Φの急激な変化により
ベース20,22に渦電流が発生する。この渦電
流による不整磁場は、トロイダルコイル14と垂
直磁場コイル18の作るプラズマ閉じ込め磁場を
乱し、プラズマ12の閉じ込め性能を著しく害す
る。このため従来は、ベース20,22を細分割
し、各部分を絶縁していた、この細分割する方式
は、構造が複雑で経済的でない上に、ベース2
0,22の剛性を弱め、核融合装置を支持するベ
ースの機能を損うおそれがあつた。
However, in the conventional torus-type fusion device,
Since the bases 20 and 22 are interlinked with the magnetic flux Φ of the air-core current transformer coil 16, eddy currents are generated in the bases 20 and 22 due to sudden changes in the magnetic flux Φ. The irregular magnetic field caused by this eddy current disturbs the plasma confinement magnetic field created by the toroidal coil 14 and the vertical magnetic field coil 18, and significantly impairs the confinement performance of the plasma 12. For this reason, in the past, the bases 20 and 22 were subdivided and each part was insulated.This method of subdividing the bases 20 and 22 was not only complicated and uneconomical, but also
There was a risk that the rigidity of the 0.0,22 would be weakened and the function of the base supporting the fusion device would be impaired.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、空心変流器コイルの磁束のう
ちベースと鎖交する成分を減らしてベースに生ず
る渦電流を減少させ、プラズマ閉じ込め磁場に乱
れのない核融合装置を提供することである。
An object of the present invention is to reduce the component of the magnetic flux of an air-core current transformer coil that interlinks with the base to reduce eddy currents generated in the base, thereby providing a nuclear fusion device in which the plasma confinement magnetic field is not disturbed.

〔問題点を解決するための手段〕[Means for solving problems]

本発明は、上記目的を達成するために、真空容
器のトーラス方向に配置されプラズマと鎖交する
磁束を発生する空心変流器コイルを、ポロイダル
断面上、真空容器を取り巻くように配置される内
側空心変流器コイル群と、その外側を取り巻くよ
うに配置され内側空心変流器コイル群とは逆方向
に励磁される外側空心変流器コイル群とで構成し
たものである。
In order to achieve the above object, the present invention provides an air-core current transformer coil that is arranged in the torus direction of a vacuum vessel and generates a magnetic flux that interlinks with the plasma. It is composed of an air-core current transformer coil group and an outer air-core current transformer coil group that is arranged to surround the outside and is excited in the opposite direction to the inner air-core current transformer coil group.

〔作 用〕[Effect]

このように内側空心変流器コイル群と外側空心
変流器コイル群とで互いに逆方向に電流が流れる
ようにすると、それらが作る磁束は外側空心変流
器コイル群の更に外側では互いに打ち消し合うの
で、ベースと鎖交する磁束は非常に少なくなる。
従つて、磁束の変化によりベースに生ずる渦電流
は極めて小さくなり、不整磁場は実質的に発生し
ない。その結果、プラズマ閉じ込め磁場の乱れの
ない核融合装置が得られる。
If current flows in opposite directions in the inner air-core current transformer coil group and the outer air-core current transformer coil group in this way, the magnetic fluxes they create will cancel each other out further outside the outer air-core current transformer coil group. Therefore, the magnetic flux interlinking with the base becomes extremely small.
Therefore, the eddy current generated in the base due to changes in magnetic flux becomes extremely small, and substantially no irregular magnetic field is generated. As a result, a fusion device without disturbance of the plasma confinement magnetic field can be obtained.

〔実施例〕〔Example〕

次に、第1図と第2図を参照して、本発明の実
施例を説明する。
Next, an embodiment of the present invention will be described with reference to FIGS. 1 and 2.

第1図は本発明の一実施例を示すポロイダル方
向の断面図である。図において、真空容器10の
内部にはプラズマ12が閉じ込められている。こ
の真空容器10の小周方向にはトロイダルコイル
14が配置され、真空容器10のトーラス方向に
は、空心変流器コイル16A,16Bが配置され
ている。空心変流器コイル16Aは、ポロイダル
断面上、外側の空心変流器コイル群を形成し、空
心変流器コイル16Bは内側の空心変流器コイル
群を形成している。従つて、本実施例の空心変流
器コイルは、外側の空心変流器コイル16Aと内
側の空心変流器コイル16Bとの二重構造になつ
ている。外側の空心変流器コイル16Aと内側の
空心変流器コイル16Bとは互いに逆方向に電流
が流れるように接続されており、その結果起磁力
が互いに逆方向になるように構成されている。真
空容器10およびコイル14,16A,16Bは
上下のベース20,22に支持されている。
FIG. 1 is a cross-sectional view in the poloidal direction showing one embodiment of the present invention. In the figure, plasma 12 is confined inside a vacuum vessel 10. A toroidal coil 14 is arranged in the circumferential direction of the vacuum vessel 10, and air-core current transformer coils 16A and 16B are arranged in the torus direction of the vacuum vessel 10. The air-core current transformer coil 16A forms an outer air-core current transformer coil group on the poloidal cross section, and the air-core current transformer coil 16B forms an inner air-core current transformer coil group. Therefore, the air-core current transformer coil of this embodiment has a double structure of an outer air-core current transformer coil 16A and an inner air-core current transformer coil 16B. The outer air-core current transformer coil 16A and the inner air-core current transformer coil 16B are connected so that currents flow in opposite directions, and as a result, the magnetomotive forces are configured to be in opposite directions. The vacuum vessel 10 and the coils 14, 16A, 16B are supported by upper and lower bases 20, 22.

このように構成された本実施例の作用は次の通
りである。
The operation of this embodiment configured in this way is as follows.

空心変流器コイル16A,16Bとが作る磁束
Φは、第1図に示すようになり、磁束Φは空心変
流器コイル16Aの外側では互いに打ち消し合
い、ほとんどの磁束が外側の空心変流器コイル1
6Aと内側の空心変流器コイル16Bとの間にく
る。特にトーラスの中心側(真空容器10の左
側)においては、大部分の磁束が外側の空心変流
器コイル16Aと内側の空心変流器コイル16B
との間に位置するようになる。従つて、ベース2
0と鎖交する磁束は非常に少なくなる。この結
果、空心変流器コイル16A,16Bの磁束Φの
変化によりベース20に生ずる渦電流は極めて小
さくなり、不整磁場は実質上発生しない。
The magnetic flux Φ produced by the air-core current transformer coils 16A and 16B is as shown in FIG. coil 1
6A and the inner air-core current transformer coil 16B. Especially on the center side of the torus (left side of the vacuum vessel 10), most of the magnetic flux is distributed between the outer air-core current transformer coil 16A and the inner air-core current transformer coil 16B.
It will be located between. Therefore, base 2
The magnetic flux interlinking with 0 becomes extremely small. As a result, the eddy current generated in the base 20 due to the change in the magnetic flux Φ of the air-core current transformer coils 16A, 16B becomes extremely small, and substantially no irregular magnetic field is generated.

第2図は本発明の他の実施例を示すポロイダル
方向の断面図である。本実施例では、トロイダル
コイル14が超電導コイルであり、このトロイダ
ルコイル14の内側に一組の空心変流器コイル1
6A,16Bが配置されている。空心変流器コイ
ル16A,16Bは第1図実施例と同様に互いに
逆方向に電流が流れるように接続されている。
FIG. 2 is a cross-sectional view in the poloidal direction showing another embodiment of the present invention. In this embodiment, the toroidal coil 14 is a superconducting coil, and a set of air-core current transformer coils 1 is installed inside the toroidal coil 14.
6A and 16B are arranged. The air-core current transformer coils 16A and 16B are connected so that current flows in opposite directions as in the embodiment of FIG.

従来、超電導コイルは強磁場内では大きな磁束
変化により熱を発生し常電導に戻り易いために使
用困難とされ、トロイダル磁場コイル14ではト
ーラス中心側の磁場が強いため、この部分に時間
的に変化する空心変流器コイルの磁束があるのは
好ましくないとされていた。
Conventionally, superconducting coils have been considered difficult to use in a strong magnetic field because they generate heat due to large changes in magnetic flux and tend to return to normal conductivity.In the toroidal magnetic field coil 14, the magnetic field on the center side of the torus is strong, so there is a temporal change in this part. It was considered undesirable to have magnetic flux in the air-core current transformer coil.

これに対し、本実施例では、空心変流器コイル
を外側の空心変流器コイル16Aと内側の空心変
流器コイル16Bとに分け、それぞれの電流方向
を互いに逆にしてあるので、磁束Φがトーラス中
心側でトロイダル磁場コイル14と鎖交しない。
このため、本実施例の超電導コイルで構成された
トロイダルコイル14は、熱損失が少なく安定に
動作する。
In contrast, in this embodiment, the air-core current transformer coil is divided into an outer air-core current transformer coil 16A and an inner air-core current transformer coil 16B, and the current directions of each are reversed, so that the magnetic flux Φ does not interlink with the toroidal magnetic field coil 14 on the torus center side.
Therefore, the toroidal coil 14 made of the superconducting coil of this embodiment operates stably with little heat loss.

第1図実施例と同様に本実施例においても、磁
束Φによるベース20の渦電流発生が少なく、不
整磁場の発生もごくわずかなので、真空容器10
内にプラズマ12を安定して閉じ込めることがで
きるのはいうまでもない。
Similar to the embodiment shown in FIG. 1, in this embodiment as well, the generation of eddy current in the base 20 due to the magnetic flux Φ is small, and the generation of an irregular magnetic field is also very small.
Needless to say, it is possible to stably confine the plasma 12 inside.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、空心変流器コイルの磁束のう
ちベースと鎖交する成分が減りベースに生ずる渦
電流が激減するので、プラズマ閉じ込め磁場に乱
れのない核融合装置が得られる。
According to the present invention, the component of the magnetic flux of the air-core current transformer coil that interlinks with the base is reduced, and the eddy current generated in the base is drastically reduced, so that a nuclear fusion device without disturbance in the plasma confinement magnetic field can be obtained.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は本発明による核融合装置の一実施例を
示すポロイダル方向の断面図、第2図はトロイダ
ルコイルに超電導コイルを用いる本発明の他の実
施例を示すポロイダル方向の断面図、第3図は従
来の核融合装置の一例を示す断面図である。 10……真空容器、12……プラズマ、14…
…トロイダルコイル、16……従来の空心変流器
コイル、16A……外側の空心変流器コイル、1
6B……内側の空心変流器コイル、18……垂直
磁場コイル、20,22……ベース。
FIG. 1 is a cross-sectional view in the poloidal direction showing one embodiment of the nuclear fusion device according to the present invention, FIG. 2 is a cross-sectional view in the poloidal direction showing another embodiment of the present invention using a superconducting coil as the toroidal coil, and FIG. The figure is a sectional view showing an example of a conventional nuclear fusion device. 10... Vacuum container, 12... Plasma, 14...
...Toroidal coil, 16... Conventional air-core current transformer coil, 16A... Outer air-core current transformer coil, 1
6B... Inner air-core current transformer coil, 18... Vertical magnetic field coil, 20, 22... Base.

Claims (1)

【特許請求の範囲】 1 プラズマを内部に封入する円環状の真空容器
と、真空容器のポロイダル方向に配置されプラズ
マを閉じ込める磁場を発生するトロイダルコイル
と、真空容器のトーラス方向に配置されプラズマ
と鎖交してプラズマを閉じ込め加熱する変化磁束
を発生する空心変流器コイルとを備えた核融合装
置において、空心変流器コイルが、ポロイダル断
面上、真空容器を取り巻くように配置される内側
空心変流器コイル群と、その外側を取り巻くよう
に配置され内側空心変流器コイル群とは逆方向に
励磁される外側空心変流器コイル群とからなるこ
とを特徴とする核融合装置。 2 特許請求の範囲第1項において、トロイダル
コイルが、前記外側空心変流器コイル群よりも外
側に配置される直径を有する超電導コイルからな
ることを特徴とする核融合装置。
[Scope of Claims] 1. An annular vacuum container that encloses plasma inside, a toroidal coil that is arranged in the poloidal direction of the vacuum container and generates a magnetic field that confines the plasma, and a toroidal coil that is arranged in the torus direction of the vacuum container that connects the plasma. In a nuclear fusion device equipped with an air-core current transformer coil that generates a changing magnetic flux that confines and heats the plasma, the air-core current transformer coil has an inner air-core current transformer coil that is arranged to surround a vacuum vessel on a poloidal cross section. A nuclear fusion device comprising a current transformer coil group and an outer air-core current transformer coil group arranged to surround the outer side of the current transformer coil group and excited in a direction opposite to that of the inner air-core current transformer coil group. 2. The nuclear fusion device according to claim 1, wherein the toroidal coil is a superconducting coil having a diameter arranged outside the outer air-core current transformer coil group.
JP10587079A 1979-08-22 1979-08-22 Nuclear fusion equipment Granted JPS5630679A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP10587079A JPS5630679A (en) 1979-08-22 1979-08-22 Nuclear fusion equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP10587079A JPS5630679A (en) 1979-08-22 1979-08-22 Nuclear fusion equipment

Publications (2)

Publication Number Publication Date
JPS5630679A JPS5630679A (en) 1981-03-27
JPS6122919B2 true JPS6122919B2 (en) 1986-06-03

Family

ID=14418978

Family Applications (1)

Application Number Title Priority Date Filing Date
JP10587079A Granted JPS5630679A (en) 1979-08-22 1979-08-22 Nuclear fusion equipment

Country Status (1)

Country Link
JP (1) JPS5630679A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS63196815U (en) * 1987-06-09 1988-12-19

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60189897A (en) * 1984-03-09 1985-09-27 日立照明株式会社 Device for firing discharge lamp
JPS6329497A (en) * 1986-07-22 1988-02-08 大和電子工業株式会社 Discharge lamp lighting circuit

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS63196815U (en) * 1987-06-09 1988-12-19

Also Published As

Publication number Publication date
JPS5630679A (en) 1981-03-27

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