JPS59231469A - Nuclear fusion device - Google Patents

Nuclear fusion device

Info

Publication number
JPS59231469A
JPS59231469A JP58105700A JP10570083A JPS59231469A JP S59231469 A JPS59231469 A JP S59231469A JP 58105700 A JP58105700 A JP 58105700A JP 10570083 A JP10570083 A JP 10570083A JP S59231469 A JPS59231469 A JP S59231469A
Authority
JP
Japan
Prior art keywords
coil
plasma discharge
discharge tube
support
voloidal
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.)
Pending
Application number
JP58105700A
Other languages
Japanese (ja)
Inventor
裕司 奥村
鈴木 史男
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 Service Engineering Co Ltd
Hitachi Ltd
Original Assignee
Hitachi Service Engineering Co Ltd
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 Service Engineering Co Ltd, Hitachi Ltd filed Critical Hitachi Service Engineering Co Ltd
Priority to JP58105700A priority Critical patent/JPS59231469A/en
Publication of JPS59231469A publication Critical patent/JPS59231469A/en
Pending 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

Landscapes

  • Lining Or Joining Of Plastics Or The Like (AREA)
  • Discharge Heating (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の利用分野〕 本発明は核融合装置に係り、特にブラズー7の制御、あ
るいは加熱を行うためにトーラス内周側と外周側に配置
されるボロイダルコイルをそのトーラス周方向の途中で
分割し、この分割端部でトーラス内周側と外周側のボロ
イダルコイルを渡り部を介して接続するフラクショナル
ターン方式を採用しているものに好適な核融合装置に関
する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a nuclear fusion device, and particularly relates to a voloidal coil arranged on the inner and outer circumferential sides of a torus in order to control or heat the Blaze 7. The present invention relates to a nuclear fusion device suitable for a nuclear fusion device that employs a fractional turn method in which the torus is divided midway in the circumferential direction and the voloidal coils on the inner and outer circumferential sides of the torus are connected via transition parts at the divided ends.

〔発明の背景〕[Background of the invention]

一般に核融合装置は第1図、及び第2図に示す如く、内
部にプラズマ1を収納する環状のプラズマ放9℃管2と
、該プラズマ放電管2を取り囲み、かつ、1・−ラス周
方向に所定間隔をもって複数個配置式れ、その発生磁界
によってプラズマ1をプラズマ放電管2内に閉じ込める
トロイダルコイル3と、前記プラズマ放電管2に《aつ
て巻回され、プラズマ1の位置制in41 、あるいは
加熱等を、その発生・磁界によって行なうポロイタ゛ル
コイル4、及び5とにより概略構成される。尚、6は変
流器コイルである。
In general, a nuclear fusion device, as shown in FIGS. 1 and 2, includes an annular plasma discharge tube 2 that houses a plasma 1 therein, and a plasma discharge tube 2 that surrounds the plasma discharge tube 2 and that has a 1. a plurality of toroidal coils 3 arranged at predetermined intervals, and confining the plasma 1 within the plasma discharge tube 2 by the generated magnetic field; It is generally composed of poloitile coils 4 and 5 that perform heating and the like by the generated magnetic field. Note that 6 is a current transformer coil.

ところで、プラズマ放電管2は、通常、第3図(a)に
示す様に2分割され、これは第3図(b)のように半円
状の2つの部分から成り立っている。そして、2分割さ
れたそれぞれのプラズマ放電管2にトロイダルコイルを
組み込み、その後、2つの分割されたプラズマ放電管2
の分割端部を突き合わせて円環状に形成される。
By the way, the plasma discharge tube 2 is usually divided into two parts as shown in FIG. 3(a), and this consists of two semicircular parts as shown in FIG. 3(b). Then, a toroidal coil is installed in each of the two divided plasma discharge tubes 2, and then the two divided plasma discharge tubes 2 are assembled.
It is formed into an annular shape by abutting the divided ends of the two.

従って、このような構成ではプラズマ放電管2とトロイ
ダルコイル3間の空間に巻回されるボロイダルコイル5
は、トーラス状に連続した状態の一itでは組み立てら
れないため、フラクショナルターンと呼ばれる方式で構
成される。
Therefore, in such a configuration, the voloidal coil 5 wound in the space between the plasma discharge tube 2 and the toroidal coil 3
Because it cannot be assembled in one piece in a continuous torus, it is constructed using a method called fractional turn.

このフラクショナルターン方式とは、ボロイダルコイル
5もプラズマ放電管2と同様に、プラズマ放電管20分
割端で、そのプラズマ放′亀管2のトーラス内周側に配
1置される内側ボロイダルコイル5aとトーラス外周側
に配置される外側ボロイダルコイル5b,を分割し、こ
の分割端で内外側ボロイダルコイル5aと5bを渡9部
7を介して電気的に接続し、分割端が半円状に2分割さ
れた状態でプラズマ放電管2に組み込まれる。この状態
で上記の如く、分割された2つのプラズマ放電管2を突
き合わせると、ボロイダルコイ41)部7は、第4図に
示す様に、相隣接するボロイダルコイル5の疫り部7が
互いに重なった状態となり、装置全体からみると、トー
ラス状に連続に巻回された場合と同様になる。
This fractional turn method means that, like the plasma discharge tube 2, the voloidal coil 5 is also an inner voloidal coil placed on the inner periphery of the torus of the plasma discharge tube 2 at the dividing end of the plasma discharge tube 20. 5a and the outer voloidal coil 5b arranged on the outer circumferential side of the torus are divided, and the inner and outer voloidal coils 5a and 5b are electrically connected at the divided end via the cross section 7, and the divided end is semicircular. The plasma discharge tube 2 is assembled into the plasma discharge tube 2 in a state where it is divided into two parts. In this state, when the two divided plasma discharge tubes 2 are butted against each other as described above, the boroidal coil 41) portion 7 is formed so that the convex portions 7 of the adjacent boroidal coils 5 are mutually connected to each other, as shown in FIG. They are in an overlapping state, and when viewed from the entire device, the result is the same as in the case of continuous winding in a torus shape.

ところが上記したフラクショナルターン方式を採用する
と、渡り部7に流れる電流の方向は第4図に矢印Iの如
く、重なり合う2つのコイル渡シ部7でそれぞれ逆向き
に流れており、この状態でトロイダルコイルの発生磁嚇
Btが渡り部7を横切ると、渡9部7には第5図、及び
第6図に示す様に、コイル渡り部7に対して法線方向の
電磁力FTが発生する。この′藏磁力FTはそれぞれ逆
向きに発生するため、従来は重なり合う2つのコイル渡
り部7をガラス繊維9等で縛り、電磁力FTに対し渡り
部7を支持していた。
However, when the above-mentioned fractional turn method is adopted, the direction of the current flowing through the transition section 7 is reversed in the two overlapping coil transition sections 7, as shown by arrow I in Fig. 4, and in this state, the toroidal coil When the generated magnetic threat Bt crosses the transition portion 7, an electromagnetic force FT is generated in the transition portion 7 in the normal direction to the coil transition portion 7, as shown in FIGS. 5 and 6. Since the magnetic forces FT are generated in opposite directions, conventionally the two overlapping coil transition portions 7 were bound with glass fibers 9 or the like to support the transition portions 7 against the electromagnetic force FT.

しかしながら、渡り部7の外側にはトロイダルコイル3
が配置されており、分割された2つのプラズマ放電管2
を突き合わせた後、トロイダルコイル3との間隙の間で
渡り部7を縛るには作業のために大きな空間が必要であ
シ、非常に作業効率が悪く、その信頼性に問題があった
However, the toroidal coil 3 is located outside the transition section 7.
is arranged, and two divided plasma discharge tubes 2
After butting them together, tying the transition portion 7 between the gap between the toroidal coil 3 and the toroidal coil 3 requires a large space for the work, resulting in very poor work efficiency and reliability problems.

〔発明の目的〕[Purpose of the invention]

本発明は上述の点に鑑み成されたもので、その第1の目
的とするところは、トロイダルコイルとプラズマ放電管
との間に配置されたボロイダルコイルであっても、作業
効率を悪くすることなく、その渡り部を電磁力から支持
でき信頼性の高い点、第2の目的とするところは、第1
の目的に加えボロイダルコイル渡り部の支持部分の強度
的問題を解決した核融合装置を提供するにある。
The present invention has been made in view of the above-mentioned points, and its first purpose is to reduce the working efficiency even if the voloidal coil is disposed between the toroidal coil and the plasma discharge tube. The second purpose is that the transition part can be supported from electromagnetic force without any damage.
In addition to the above object, it is an object of the present invention to provide a nuclear fusion device which solves the strength problem of the support part of the boroidal coil transition part.

〔発明の概要〕[Summary of the invention]

本発明は内部にプラズマを閉じ込め保持する環状のプラ
ズマ放電管に沿ってトーラス内周側と外周側にそれぞれ
配置されるボロイダルコイルがその周方向途中で分割さ
れ、該分割端で内周側コイルと外周側コイルが接続され
るポロイダルコイル渡シ部が位置するプラズマ放電管の
近傍にサポートを設け、該サポートでボロイダルコイル
の渡り部を支持することにより第1の目的を、更に上記
構成に加えそのサポートヲダブテールキーでプラズマ放
電管に固定することにより第2の目的を達成するように
なしたものである。
In the present invention, voloidal coils arranged on the inner circumferential side and the outer circumferential side of the torus along an annular plasma discharge tube that confines and retains plasma inside are divided in the middle in the circumferential direction, and the inner circumferential coil is separated at the dividing end. In addition to the above configuration, a support is provided near the plasma discharge tube where the poloidal coil transition part to which the outer peripheral side coil is connected is located, and the support supports the poloidal coil transition part. The second purpose is achieved by fixing the support to the plasma discharge tube with a dovetail key.

〔発明の実施例〕[Embodiments of the invention]

以下、図示しだ実施例に基づいて本発明の詳細な説明す
る。尚、7」−月はCIYE来と同一のものは同符号を
使用する。
Hereinafter, the present invention will be described in detail based on the illustrated embodiments. In addition, the same symbol is used for the month "7" which is the same as in CIYE.

I)J’: 7図、及び、■8図に本発明の一実施例を
示す。
I) J': An embodiment of the present invention is shown in Fig. 7 and Fig. ①8.

本実施例での核融合装置δの、慨略構成は、従来のもの
とほとんど同様のため、ここでの詳細説明は省略し本発
明に関連する部分のみの説明とする。
Since the general structure of the nuclear fusion device δ in this embodiment is almost the same as that of the conventional device, a detailed explanation will be omitted here and only the parts related to the present invention will be explained.

該図の如く、本実施例ではボロイダルコイル5の渡り都
7が位1〆Lするプラズマ放電管2の近傍にサポート1
0を設け、このサポート10でボロイダルコイル5の渡
り部7を支持するようにしている。このサポート10の
構造、及びサポート10による渡り部7の支持のし方を
第9図、及び第10図を用いて説v1]する。
As shown in the figure, in this embodiment, a support 1 is placed near the plasma discharge tube 2 where the crossing point 7 of the voloidal coil 5 is located 1〆L.
0 is provided, and this support 10 supports the transition portion 7 of the voloidal coil 5. The structure of this support 10 and how the transition portion 7 is supported by the support 10 will be explained using FIGS. 9 and 10 v1].

第9図に示す様に、サポートは断面り字型を成し、これ
が逆り字型の状態でプラズマ放電g2の分割端の各々に
取付けられている。逆り字型ザボ−)10aでは、相隣
接するボロイダルコイルの渡シ部を重ね合せた場合上側
に位置するコイル渡り部7aを支持し、他の逆り字型サ
ポート10bでは渡り部を重ね合せた場合下側に位置す
るコイル渡り部7bを支持している。この状態でプラズ
マ放電管2の分割端部同志を突合せると、第10図に示
す様に逆り字型サポート10aと10bも突合わされ、
コイル渡り部7aと7bが互いに重なり合い、しかも、
その周囲を逆り字型サポート10a1及び10bで覆う
ように構成される。
As shown in FIG. 9, the supports have an inverted cross section and are attached to each of the divided ends of the plasma discharge g2 in an inverted shape. The inverted-shaped support 10a supports the coil transition part 7a located on the upper side when the transition parts of adjacent voloidal coils are overlapped, and the other inverted-shaped support 10b supports the overlapping transition parts. When combined, they support the coil transition portion 7b located on the lower side. When the divided ends of the plasma discharge tube 2 are butted together in this state, the inverted-shaped supports 10a and 10b are also butted together, as shown in FIG.
The coil transition portions 7a and 7b overlap each other, and
It is configured to be surrounded by inverted-shaped supports 10a1 and 10b.

従って、本実施例の構成とすることにより、コイル渡り
部はサポートによりプラズマ放電管に支持されているた
め、電磁力が加わっても十分にこれを支えることができ
、しかも、組立時にサポート回りの作業、即ちフラクシ
ョナルターン組立後の作業がなくなり作業効率が向上し
、せまい空間であっても十分に支持できるため信頼性が
向上する効果がある。
Therefore, with the configuration of this embodiment, the coil transition section is supported by the plasma discharge tube by the support, so it can sufficiently support it even if electromagnetic force is applied. Work, that is, work after fractional turn assembly is eliminated, improving work efficiency, and even in a narrow space, sufficient support can be provided, which has the effect of improving reliability.

第11図、及び第12図にサポート構成の他の例を示す
。該図の如く、本実施例のサポー) 11a、及び11
. bもプラズマ放電管20分割端の各々に成句けられ
ている。そして、各サポートiia。
Other examples of support configurations are shown in FIGS. 11 and 12. As shown in the figure, support for this embodiment) 11a and 11
.. b is also written on each of the 20 divided ends of the plasma discharge tube. And each support IIA.

11(〕の先端にはインn−に設け、両サポート11、
3とllb全連結し、かつ、コイル渡り部7aと7bk
押える押え板120両先端にもインローを設けておき1
.一方のサポートllaに押え板12の一瑞乞着し込ん
でおく。この伏嘘でサボ)11aでは、相隣嬢するボロ
イダルコイルの渡り部を重ね合せた場合に上側に立置す
るコイル畝り部7aを支持し、他のザ=」i−トi1b
で渡p部を重ね合せた場合下側に位置するコイル渡り部
7bを支持している。この状態でプラズマ放電管20分
割端部同志を突合せると、第12図に示す様に、押え板
12の他端とサボー)11L+とのインロ一部が嵌合し
、コイル渡り部7aと7bが互いに重なり合い、その周
囲はサポート11a。
11 () is provided at the tip of the in-n-, both supports 11,
3 and llb are fully connected, and the coil transition portions 7a and 7bk
A spigot is also provided at both ends of the presser plate 120.
.. Push one part of the presser plate 12 into one support lla. In this case, when the transition parts of the adjacent voloidal coils are overlapped, the coil ridge part 7a, which is placed upright on the upper side, is supported by the coil ridge part 7a, and the other part 11a is
When the crossing p parts are overlapped, the coil crossing part 7b located on the lower side is supported. When the divided ends of the plasma discharge tube 20 are butted against each other in this state, as shown in FIG. overlap each other, and the surroundings are supports 11a.

11b1及び押え板12で橿われて構成される。11b1 and a holding plate 12.

このような構成でも、その効果は上述した実施例と同様
で、しかも本実施例では押え板12とサポートiia、
llb間は剛結合でないため、曲することができる。尚
、押え板12はプラズマ放電管2の断面にiFlって、
円筒状の連続体とすることにより、コイル渡り部に発生
する電磁力は全て押え板12のフープ力として支持する
ことができ、強度的に更に信頼性を向上さ硝ることかで
きる。
Even with such a configuration, the effect is similar to that of the above-mentioned embodiment, and in this embodiment, the presser plate 12, support iia,
Since there is no rigid connection between llb and llb, it can be bent. Note that the holding plate 12 has iFl on the cross section of the plasma discharge tube 2.
By forming a cylindrical continuous body, all the electromagnetic force generated in the coil transition portion can be supported as a hoop force of the holding plate 12, and reliability can be further improved in terms of strength.

ところで、プラズマ放tlt管とサポートの取付けは溶
接でも行えるが、溶接ではサポート内にあるコイル渡9
部導体、及び絶縁物等を熱的に劣化させる恐れがあり、
一般にはボルトを用いて固定し。
By the way, the plasma emitting TLT tube and the support can be attached by welding, but welding does not allow the coil crossing 9 inside the support to be attached.
There is a risk of thermal deterioration of conductors and insulators, etc.
Generally fixed using bolts.

ている。ところが、ボルトではその許容引張荷重を越え
ることが多々あり1強度的な信頼性に問題がある。即ち
、サポートには非常に大きな電磁力が作用するため、サ
ポートの固定も十分な強度を持つ必要がある。固定部分
に加わる力は引張り力のみであるから、強度を上げるに
は固定部分の断面積を増(2てやればよい。ボルトで固
定する場合は、ボルト本数を僧して断:■積を太きくす
ることが考えられるが、この方式ではポルi取り付ける
ために大きな空間が必要となり、上記核融合装置の構成
には不向きである。
ing. However, with bolts, the tensile load often exceeds the allowable tensile load, and there is a problem with reliability in terms of strength. That is, since a very large electromagnetic force acts on the support, the support must also be fixed with sufficient strength. The force applied to the fixed part is only tensile force, so to increase the strength, increase the cross-sectional area of the fixed part (2).When fixing with bolts, increase the number of bolts and increase the cross-sectional area: Although it is conceivable to make the diameter thicker, this method requires a large space to attach the pole i, and is not suitable for the configuration of the above-mentioned nuclear fusion device.

以下に示す例は、サポートの取り付けに大きな空間を必
要としないで断面積が大きく取れ、サポートの固定部分
の強度的問題を解決しようとするものである。即ち、第
13図、及び第14図に示す様に、逆り字型サボー)1
0a、10bをプラズマ放電管2の分割端部にダブテー
ルキー13によって固定している。このダブテールキー
13の形状を第15図に示すが、これは逆り字型サボー
)10a、10bとプラズマ放電管2に跨って設けられ
るダブテール溝に介在されるものである。
The example shown below allows for a large cross-sectional area without requiring a large space for mounting the support, and is intended to solve the strength problem of the fixed portion of the support. That is, as shown in FIGS. 13 and 14, the inverted-shaped sabot) 1
0a and 10b are fixed to the divided ends of the plasma discharge tube 2 by dovetail keys 13. The shape of this dovetail key 13 is shown in FIG. 15, and it is interposed in a dovetail groove provided across the inverted sabots 10a, 10b and the plasma discharge tube 2.

このように、ダブテールキー13でザボートヲプラズマ
放電管に固定すると、ダブテールキー13の電磁力FT
を受ける断面積A(−)は、A=LXW で表わされる。ダブテールキー13の長、さLは、サポ
ートの厚みまで長くすることができ、従って、電磁力F
Tを受ける断@積へが大きくとれ、サポートの固定部分
の強度が向上する。
In this way, when the dovetail key 13 is fixed to the plasma discharge tube, the electromagnetic force of the dovetail key 13 is
The cross-sectional area A(-) subjected to this is expressed as A=LXW. The length of the dovetail key 13, length L, can be increased up to the thickness of the support, so that the electromagnetic force F
The cross section that receives T can be greatly increased, and the strength of the fixed part of the support is improved.

〔発明の効果〕〔Effect of the invention〕

以上説明した本発明の核融合装置によれば、内部にプラ
ズマを閉じ込め保持する環状のプラズマ放電管に沿って
トーラス内周側と外周側にそれぞれ配置されるボロイダ
ルコイルがその周方向途中で分割され、該分割端で内周
側コイルと外周側コイルが接続されるポロイダルコイル
渡9部が位置するプラズマ放電管の近傍にサボー)k設
け、該サポートでボロイダルコイルの渡り部を支持した
ものであるから、フラクショナルターン組立後の作業が
なくなシ作業効率が向上し、かつ、電磁力が加ってもボ
ロイダルコイルの渡り部はサポートによシ支持されてお
り信頼性が高い。また、上記サポートをプラズマ放電管
にダブテールキーによって固定することにより、上述の
効果に加えサポートの固定部分における強度が向上し、
更に信頼性が増す此種核融合装置を得ることができる。
According to the nuclear fusion device of the present invention described above, the voloidal coils, which are arranged on the inner circumferential side and the outer circumferential side of the torus along the annular plasma discharge tube that confines and holds plasma inside, are divided in the middle in the circumferential direction. A support is provided in the vicinity of the plasma discharge tube where the poloidal coil bridge 9 is located where the inner and outer coils are connected at the split end, and the support supports the poloidal coil bridge. Because of this, there is no work to be done after fractional turn assembly, improving work efficiency, and even if electromagnetic force is applied, the transition portion of the voloidal coil is supported by the support, resulting in high reliability. Furthermore, by fixing the support to the plasma discharge tube with a dovetail key, in addition to the above-mentioned effects, the strength of the fixed part of the support is improved,
It is possible to obtain this type of nuclear fusion device with further increased reliability.

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

第1図は一般的なトカマク型の核融合装置を示す縦断面
図、第2図は一部1祈而して示す第1図の平面図、第3
図(a)は分割されたプラズマ放電管に沿ってフラクシ
ョナルターン方式のポロイダルコイルルを巻回した状態
を示す平面図、第3図(b)は第3図(a)における分
割端の正面図、第4図はフラクショナルターン方式を採
用しているボロイダルコイル渡り部の斜視図、第5図は
ボロイダルコイル渡り部を支持している従来例を示す正
面図、第6図は第5図の渡り部分の断面図、第7図は本
発明におけるボロイダルコイル渡り部の支持の一実施例
を示す正面図、第8図は分割端部近傍の平面図、第9図
は本発明に採用されるサポートの一例を示し、組立前の
断面図、第10図は第9図の組立後の断面図、第11図
は本発明に採用されるサポートの他の例を示し、組立前
の14フ〒面図、第12図は第11図の組立後の断面図
、第13図はサポートをプラズマ放電管に固定する一例
を示す断面図、第14図は第13図のボロイダルコイル
渡り部の断面図、第15図は第13図、第14図の例に
採用されるダブテールキーの斜視図である。 1・・・プラズマ、2・・・プラズマ放電管、3・・・
トロイダルコイル、5・・・ボロイダルコイル、5a−
・・トーラス内周側ポロイダルコイル、5b・・・トー
ラス外周側ポロイダルコイル、7.7a、7b・・・ボ
ロイダルコイル渡υ部、10.Ila、llb・・・サ
ポート、1.08. 10 b・・・逆り字状サポート
、12々ン J 図taノ / 第4m
Figure 1 is a vertical cross-sectional view showing a general tokamak-type nuclear fusion device, Figure 2 is a plan view of Figure 1 partially showing
Figure (a) is a plan view showing a state in which a fractional turn type poloidal coil is wound along a divided plasma discharge tube, Figure 3 (b) is a front view of the divided end in Figure 3 (a), Figure 4 is a perspective view of a voloidal coil transition section that uses the fractional turn method, Figure 5 is a front view of a conventional example supporting the voloidal coil transition section, and Figure 6 is the same as that of Figure 5. FIG. 7 is a front view showing an example of supporting the boroidal coil transition portion in the present invention, FIG. 8 is a plan view of the vicinity of the split end, and FIG. 9 is a cross-sectional view of the transition portion adopted in the present invention. FIG. 10 is a cross-sectional view of FIG. 9 after assembly, and FIG. 12 is a cross-sectional view of the assembly shown in FIG. 11, FIG. 13 is a cross-sectional view showing an example of fixing the support to the plasma discharge tube, and FIG. 14 is a cross-sectional view of the boroidal coil transition section of FIG. 13. The sectional view, FIG. 15, is a perspective view of the dovetail key employed in the examples of FIGS. 13 and 14. 1... Plasma, 2... Plasma discharge tube, 3...
Toroidal coil, 5... Voloidal coil, 5a-
... Poloidal coil on the inner circumference side of the torus, 5b... Poloidal coil on the outer circumference side of the torus, 7.7a, 7b... Voloidal coil transition section, 10. Ila,llb...Support, 1.08. 10 b...Inverted support, 12 J Figtano/4th m

Claims (1)

【特許請求の範囲】 ■。内部にプラズマを閉じ込め保持する環状のプラズマ
放電管と、該プラズマ放電管を取り囲み、かつ、トーラ
ス周方向に所定間隔をもって複数個配置されたトロイダ
ルコイルと、該トロイダルコイルと前記プラズマ放電管
との間で、かつ、該プラズマ放電管に沿って配置され、
前記プラズマの制御、あるいは加熱を行うボロイダルコ
イルとを備え、前記ボロイダルコイルはトーラス内周側
と外周側のそれぞれに配装置されると共に、その各々は
周方向途中で分割され、該分割端部で前記内周側コイル
と外周側コイルを渡り部を介して接続し、かつ、相隣接
する前記渡9部を互いに重ねて形成される核融合装置に
おいて、前記ポロイダルコイル渡り部が位置するプラズ
マ放電管の近傍にサポートを設け、該サポートでボロイ
ダルコイルの渡り部を支持したことを特徴とする核融合
装置。 2、前記プラズマ放電管はトーラス周方向途中で二分割
され、該プラズマ放電管の分割部とほぼ同一位置で前記
ボロイダルコイルが分割されていることを特徴とする特
許請求の範囲第1°項記載の核融合装置。 3、前記サポートは逆り字型状態で前記プラズマ放電管
の分割端の各々に取付けられ、該逆り字型サポートの一
方で前記相隣接するボロイダルコイル渡り部を重ね合せ
た状態で上側に位置するコイル渡り部を支持し、他方の
逆し’4−型ザボートで下側に位置するコイル渡り部を
支持すると共に、前記プラズマ放電管の分割端部同志を
突合せた際に前記コイル渡9部が互いに重なυ合い、か
つ、その周囲を前記各逆り字型サポートで覆うように構
成されていることを特徴とする特許請求の範囲第2項記
載の核融合装置。 4、前記サポートは前記プラズマ放電管の分割端の各々
に取付けられ、該サポートの一方で前記分割ボロイダル
コイル渡υ部の重ね合せた状態で上側に位置するコイル
渡9部を支持し、他方のサポートで下側に位置するコイ
ル渡り部を支持すると共に、両サポート間を押え板で連
結し、前記プラズマ放電管の分割端部同志を突合せた際
に前記コイル・1−乏り部が互いに重なり合い、かつ、
その周囲を前記谷ザボートと押え仮で覆うように第1り
成されているととを′時機とする′41:許、1′g求
の範囲第2項記載の核葭合装置。 5゜前1己1甲えイ反とサポートとの、晒結部にインロ
ーを設置r−f 、、該インロ一部を介して押え板の一
端を一方のリーボ−トに取付け、この状態で前記プラズ
マ放′的管の分割、Iji、i部を突合せて押え板の他
端を他方のサポートに取付けることを特徴とする特許請
求の111へ(IIIi:楢4項記載の核燻合装置。 6、前記押え板は円筒状の連続体で形成されていること
を特徴とする特許請A(の範囲第4項、又は第5項記載
の核融合装置。 7゜内部にプラズマを閉じ込め保持する環状のプラズマ
放電管と、該プラズマ放電管を取り囲み、かつ、トーラ
ス同方向に所定間隔をもって複数個配(役されたトロイ
ダルコイルと、該トロイダルコイルと前記プラズマ放電
管との間で、かつ、該プラズマ放電管に母って配置され
、前記プラズマの:!3制御、らるいは加熱を行うボロ
イダルコイルとを備え、前記ボロイダルコイルはトーラ
ス内周側と外周側のそれぞれに配置されると共に、その
各々は周方向途中で分割され、該分割端部で前記内周側
コイルと外1;!73 il:jコイルを渡り部を介し
て接続し、かつ、相隣接する前記渡り部を互いに重ねて
形成される核融合装+i汁において、前記プラズマ放電
管のポロイダルコイル槻り部が位1行する近傍にサポー
トをダブテールキーによって固定し、該サポートでボロ
イダルコイルの7)史り部を支持したことを特徴とする
核融合装置程。 8゜前記ダブテールキーは、前記サポートとプラズマ放
電管の両者に跨って形成されるダブテール溝に介在され
ることを特徴とする特許 第7項記載の核融合装置。
[Claims] ■. An annular plasma discharge tube that confines and holds plasma inside, a plurality of toroidal coils surrounding the plasma discharge tube and arranged at predetermined intervals in the circumferential direction of the torus, and between the toroidal coil and the plasma discharge tube. and arranged along the plasma discharge tube,
and a voloidal coil that controls or heats the plasma, and the voloidal coil is arranged on the inner circumferential side and the outer circumferential side of the torus, and each of the voloidal coils is divided in the middle in the circumferential direction, and the divided end In a nuclear fusion device formed by connecting the inner circumference side coil and the outer circumference side coil through a transition part at a part, and stacking adjacent said transition parts on top of each other, the plasma discharge where the poloidal coil transition part is located. A nuclear fusion device characterized in that a support is provided near the tube, and the transition portion of the boroidal coil is supported by the support. 2. The plasma discharge tube is divided into two along the circumferential direction of the torus, and the voloidal coil is divided at substantially the same position as the divided portion of the plasma discharge tube. The described fusion device. 3. The support is attached to each of the split ends of the plasma discharge tube in an inverted shape, and one side of the inverted support is attached to the upper side with the adjacent voloidal coil transition portions overlapped. The other inverted '4-shaped Zabot supports the lower coil transition part, and when the divided ends of the plasma discharge tube are brought together, the coil transition part 9 is supported. 3. The nuclear fusion device according to claim 2, wherein the parts overlap each other, and the periphery thereof is covered by each of the inverted-shaped supports. 4. The support is attached to each of the split ends of the plasma discharge tube, and one of the supports supports the coil span 9 section located on the upper side in an overlapping state of the split voloidal coil span υ section, and the other support The lower coil transition part is supported by the support, and the two supports are connected by a presser plate, so that when the divided ends of the plasma discharge tube are butted together, the coil 1-deficient part is mutually connected. overlap, and
1. The nuclear reel fitting device according to item 2, wherein the first frame is formed so as to cover the periphery with the valley support and the presser foot. 5゜Install a spigot at the bleached joint between the 1st leg and the support r-f.Attach one end of the presser plate to one of the leeboards through a part of the spigot, and in this state. Claim 111 (IIIi: Nuclear smoker according to claim 4), characterized in that the divided, Iji, and i parts of the plasma radiation tube are butted against each other and the other end of the presser plate is attached to the other support. 6. The nuclear fusion device according to claim 4 or 5 of patent claim A, characterized in that the holding plate is formed of a cylindrical continuous body. 7. Contains and maintains plasma inside. an annular plasma discharge tube; a plurality of toroidal coils surrounding the plasma discharge tube and arranged at predetermined intervals in the same direction of the toroid; and between the toroidal coil and the plasma discharge tube; A voloidal coil is arranged next to the plasma discharge tube and performs control and heating of the plasma, and the voloidal coil is arranged on the inner and outer sides of the torus. , each of them is divided in the middle in the circumferential direction, and at the divided end, the inner coil and the outer coil are connected via a transition portion, and the adjacent transition portions are connected to each other. In the nuclear fusion device + i-juice that is formed in an overlapping manner, a support is fixed with a dovetail key in the vicinity of the poloidal coil encircling portion of the plasma discharge tube in one row, and the support supports the 7) history portion of the voloidal coil with the support. 8. The nuclear fusion device according to Patent No. 7, characterized in that the dovetail key is interposed in a dovetail groove formed across both the support and the plasma discharge tube. fusion device.
JP58105700A 1983-06-15 1983-06-15 Nuclear fusion device Pending JPS59231469A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58105700A JPS59231469A (en) 1983-06-15 1983-06-15 Nuclear fusion device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58105700A JPS59231469A (en) 1983-06-15 1983-06-15 Nuclear fusion device

Publications (1)

Publication Number Publication Date
JPS59231469A true JPS59231469A (en) 1984-12-26

Family

ID=14414641

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58105700A Pending JPS59231469A (en) 1983-06-15 1983-06-15 Nuclear fusion device

Country Status (1)

Country Link
JP (1) JPS59231469A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US10580535B2 (en) 2017-01-30 2020-03-03 Tokamak Energy Ltd. Tokamak with poloidal field coil arrangement for double null merging ignition, method therefor and nuclear fusion reactor with the same

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US10580535B2 (en) 2017-01-30 2020-03-03 Tokamak Energy Ltd. Tokamak with poloidal field coil arrangement for double null merging ignition, method therefor and nuclear fusion reactor with the same

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