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JPH0126036B2 - - Google Patents
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JPH0126036B2 - - Google Patents

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Publication number
JPH0126036B2
JPH0126036B2 JP58045948A JP4594883A JPH0126036B2 JP H0126036 B2 JPH0126036 B2 JP H0126036B2 JP 58045948 A JP58045948 A JP 58045948A JP 4594883 A JP4594883 A JP 4594883A JP H0126036 B2 JPH0126036 B2 JP H0126036B2
Authority
JP
Japan
Prior art keywords
discharge tube
toroidal
coil
fusion device
nuclear fusion
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
JP58045948A
Other languages
Japanese (ja)
Other versions
JPS59171884A (en
Inventor
Mitsuru Ikeda
Kazuo Kuroishi
Shohei Suzuki
Takao Suzuki
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 JP58045948A priority Critical patent/JPS59171884A/en
Publication of JPS59171884A publication Critical patent/JPS59171884A/en
Publication of JPH0126036B2 publication Critical patent/JPH0126036B2/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

Landscapes

  • Plasma Technology (AREA)

Description

【発明の詳細な説明】 〔発明の利用分野〕 本発明は、ドーナツ状の放電管に巻回して形成
された複数のトロイダルコイルを、放電管のポロ
イダル方向に略等間隔に配置した核融合装置に関
する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention provides a nuclear fusion device in which a plurality of toroidal coils formed by winding around a donut-shaped discharge tube are arranged at approximately equal intervals in the poloidal direction of the discharge tube. Regarding.

〔従来技術〕[Prior art]

核融合装置は、放電管の内部にプラズマを閉じ
込めるために磁界を使用している。そして、ドー
ナツ状の放電管を用いるトーラス型の核融合装置
においては、マルチポール型とする場合に放電管
中に数本のポロイダルコイルと呼ばれるコイルを
配置している。このポロイダルコイルは、放電管
と同心状に配置され、コイルに大電流が流れるこ
とにより同心磁界を発生させ、プラズマを圧縮し
て放電管内に閉じ込めるようになつている。ま
た、放電管の周囲のポロイダル方向に巻回して形
成したトロイダルコイルを用い、放電管のトロイ
ダル方向に磁界を加えプラズマの閉じ込めの安定
化を図つている。更に、放電管内にはポロイダル
コイルと並行して放電管と同心状に乱流加熱コイ
ルが設けてある。この乱流加熱コイルは、短パル
ス電流が流されてプラズマ中に短パルスの乱電流
を作り、プラズマを加熱するようになつている。
Fusion devices use magnetic fields to confine plasma inside a discharge tube. In a torus-type nuclear fusion device using a donut-shaped discharge tube, several coils called poloidal coils are arranged in the discharge tube in the case of a multipole type. This poloidal coil is arranged concentrically with the discharge tube, and when a large current flows through the coil, a concentric magnetic field is generated to compress the plasma and confine it within the discharge tube. In addition, a toroidal coil wound in a poloidal direction around the discharge tube is used to apply a magnetic field in the toroidal direction of the discharge tube to stabilize plasma confinement. Furthermore, a turbulent heating coil is provided within the discharge tube in parallel with the poloidal coil and concentrically with the discharge tube. This turbulent heating coil is designed to generate short pulses of turbulent current in the plasma by passing a short pulse of current through it, thereby heating the plasma.

第1図は、従来のトロイダルコイルの配置、接
続状態を示す説明図である。第1図においてドー
ナツ状をなす放電管10の周囲には、トロイダル
コイルを構成するソレノイド12が放電管10の
ポロイダル方向に巻回されて形成された複数のソ
レノイド12が放電管10のトロイダル方向に略
等間隔をもつて配置されている。そして、複数の
ソレノイド12は、渡り線14により例えば時計
方向に順次直列に接続され、電源16から磁界発
生用の電流を受けるようになつている。また、放
電管10の内部には、図示しないポロイダルコイ
ルと共に乱流加熱コイル18が設けられ、乱流加
熱コイル用電源20に接続されて、プラズマを加
熱できるようになつている。
FIG. 1 is an explanatory diagram showing the arrangement and connection state of a conventional toroidal coil. In FIG. 1, around the donut-shaped discharge tube 10, a plurality of solenoids 12 formed by winding the solenoids 12 constituting a toroidal coil in the poloidal direction of the discharge tube 10 extend in the toroidal direction of the discharge tube 10. They are arranged at approximately equal intervals. The plurality of solenoids 12 are connected in series in a clockwise direction, for example, by connecting wires 14, and receive current for generating a magnetic field from a power source 16. Further, a turbulent heating coil 18 is provided inside the discharge tube 10 together with a poloidal coil (not shown), and is connected to a turbulent heating coil power source 20 to heat the plasma.

このような核融合装置においては、乱流加熱コ
イル18が発生する高周波変化磁界がトロイダル
コイルを形成する各ソレノイド間の接続部(渡り
線14の部分)に透起電圧を生み、各接続部に生
じた透起電圧が電源16に総量として大きな負荷
を及ぼす危険性を有している。また、トロイダル
コイルとアース間に大きな電圧差を生む欠点を有
している。
In such a nuclear fusion device, the high-frequency changing magnetic field generated by the turbulent heating coil 18 generates a transmissive voltage at the connection between the solenoids forming the toroidal coil (the crossover wire 14), and There is a risk that the generated electromotive voltage will impose a large total load on the power supply 16. It also has the disadvantage of creating a large voltage difference between the toroidal coil and ground.

そこで、第2図に示すように反時計方向に巻き
戻したループ22を設け、トロイダルコイルに生
ずる誘起電圧を打ち消すようにしている。しか
し、このような構造の核融合装置にあつては、電
源16にかかる負荷はなくなるが、アースと折返
部24との間には依然として大きな電圧差が生ず
る。
Therefore, as shown in FIG. 2, a loop 22 wound counterclockwise is provided to cancel the induced voltage generated in the toroidal coil. However, in a nuclear fusion device having such a structure, although there is no load on the power source 16, a large voltage difference still occurs between the ground and the folded portion 24.

〔発明の目的〕[Purpose of the invention]

本発明は、トロイダルコイル電源部に負荷を与
えることなく、トロイダルコイルとアースとの間
に生ずる電圧差を低減することができる核融合装
置を提供することを目的とする。
An object of the present invention is to provide a nuclear fusion device that can reduce the voltage difference between the toroidal coil and the ground without applying a load to the toroidal coil power supply section.

〔発明の概要〕[Summary of the invention]

本発明は、ドーナツ状の放電管10のトロイダ
ル方向に沿つて設けた複数のトロイダルコイルを
複数の組に分割し、これらのトロイダルコイルに
電流を供給する電源を磁場の影響を受けない位置
に設けることにより、上記目的を達成できるよう
に構成したものである。
In the present invention, a plurality of toroidal coils provided along the toroidal direction of a donut-shaped discharge tube 10 are divided into a plurality of groups, and a power source for supplying current to these toroidal coils is provided at a position not affected by the magnetic field. Thus, the above object can be achieved.

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

本発明に係る核融合装置の好ましい実施例を、
添付図面に従つて詳説する。なお、前記従来技術
において説明した部分に対応する部分について
は、同一の符号を付しその説明を省略する。
A preferred embodiment of the nuclear fusion device according to the present invention is as follows:
A detailed explanation will be given according to the attached drawings. Note that the same reference numerals are given to the parts corresponding to the parts explained in the prior art, and the explanation thereof will be omitted.

放電管10のトーラス方向に略等間隔をもつて
配置された複数、例えば8個のソレノイド12
a,12b,12c,12d,12e,12f,
12g,12hは、12a〜12dが1組をな
し、12e〜12hが1組をなすように分割され
ている。そして、ソレノイド12bとソレノイド
12cとから電源16に接続する口出し線26,
28が引き出され、ソレノイド12fとソレノイ
ド12gとからそれぞれ電源16に接続する口出
し線30,32が引き出されている。更に、ソレ
ノイド12aとソレノイド12dとは接続線34
により結合され、ソレノイド12eとソレノイド
12hとは接続線36により接続されている。
A plurality of, for example eight, solenoids 12 arranged at approximately equal intervals in the torus direction of the discharge tube 10.
a, 12b, 12c, 12d, 12e, 12f,
12g and 12h are divided such that 12a to 12d form one set and 12e to 12h form one set. A lead wire 26 connecting the solenoid 12b and the solenoid 12c to the power source 16,
28 is pulled out, and lead wires 30 and 32 are pulled out from the solenoid 12f and the solenoid 12g, respectively, to connect to the power source 16. Furthermore, the solenoid 12a and the solenoid 12d are connected to a connecting wire 34.
The solenoid 12e and the solenoid 12h are connected by a connecting line 36.

このような実施例にあつては、乱流加熱コイル
18に短パルス電流が流れた場合においても、電
源16,16に負荷がかからないばかりでなく、
折返部38a,38b,40a,40bにおける
アース管電圧が乱流加熱コイル電圧の1/4に低減
分散される。
In such an embodiment, even when a short pulse current flows through the turbulent heating coil 18, not only is there no load on the power supplies 16, 16, but
The earth tube voltage at the folded portions 38a, 38b, 40a, and 40b is reduced and dispersed to 1/4 of the turbulent heating coil voltage.

更に、第4図に示す如く、口出し線26,2
8,30,32をポロイダル磁場の影響のない装
置から離れた場所において直列に接続し、電源を
1つとすることができる。このように電源を1つ
とすることにより、各ソレノイドの同調を図るこ
とが容易となる。
Furthermore, as shown in FIG.
8, 30, and 32 can be connected in series at a location away from the device where they are not affected by the poloidal magnetic field, and a single power source can be used. By using one power source in this way, it becomes easy to synchronize each solenoid.

第5図および第6図は、本発明に係る核融合装
置の他の実施例を示したものである。第5図に示
した実施例は、各ソレノイド12a〜12hを4
個の組に分割した例を示したもので、口出し線は
各組をなすソレノイドの中間(例えばソレノイド
12aとソレノイド12bとの中間)から引き出
すようになつており、接続線42,44,46,
48が各組のソレノイド同志を接続している。こ
のように、ソレノイドの組数は、3個以上とする
ことができ、ソレノイドに生ずる誘起電圧とアー
スとの間の電位差は、各組数の逆数以下にするこ
とができる。また、各組から引き出す口出し線
は、各組における口出し線の左右のソレノイドが
同数となる位置が望ましいが、ソレノイド数が異
なつていても差し支えない。この場合、各組の両
端とアースとの間の電圧差は、口出し線の左右の
コイル数の比に分配される。
FIGS. 5 and 6 show other embodiments of the nuclear fusion device according to the present invention. The embodiment shown in FIG. 5 has four solenoids 12a to 12h.
This figure shows an example in which the solenoid is divided into two groups, and the lead wire is drawn out from the middle of the solenoid forming each group (for example, the middle between the solenoid 12a and the solenoid 12b), and the connecting wires 42, 44, 46,
48 connects each set of solenoids. In this way, the number of sets of solenoids can be three or more, and the potential difference between the induced voltage generated in the solenoid and the ground can be made equal to or less than the reciprocal of each number of sets. Furthermore, it is preferable that the lead wires drawn out from each set are located at positions where the number of solenoids on the left and right sides of the lead wires in each set is the same, but the number of solenoids may be different. In this case, the voltage difference between both ends of each set and the ground is distributed to the ratio of the number of coils on the left and right sides of the lead wire.

前記各実施例においては、巻き戻しをただ1巻
きのループにし、各ソレノイド12a〜12hを
流れる電流が全て時計回りであつたため、小部分
についてみれば、図面に垂直な方向に磁場が存在
する。そこで、例えば第6図に示した実施例のよ
うにソレノイドを流れる電流が時計回り、反時計
回りと交互に流れるように各ソレノイド間を接続
することにりり、図面に垂直な方向の磁場を打ち
消すことができ、乱流加熱コイルの作動に伴うソ
レノイドに生ずる磁場の影響をプラズマに与える
ことなくプラズマを加熱することができる。
In each of the embodiments described above, the unwinding is performed in a loop with only one turn, and the currents flowing through the solenoids 12a to 12h are all clockwise. Therefore, in a small portion, a magnetic field exists in a direction perpendicular to the drawing. Therefore, for example, as in the embodiment shown in Fig. 6, it is decided to connect the solenoids so that the current flowing through the solenoids flows alternately clockwise and counterclockwise, thereby canceling out the magnetic field in the direction perpendicular to the drawing. The plasma can be heated without being affected by the magnetic field generated in the solenoid due to the operation of the turbulent heating coil.

〔発明の効果〕〔Effect of the invention〕

以上説明したように本発明によれば、トロイダ
ルコイルを複数の組に分割し、これらトロイダル
コイルに電流を供給する電源を磁場の影響を受け
ない位置に設けることにより、電源に負荷を与え
ることなくトロイダルコイルとアースとの間の電
位差を低減することができる。
As explained above, according to the present invention, the toroidal coil is divided into a plurality of groups, and the power source that supplies current to these toroidal coils is provided in a position that is not affected by the magnetic field, thereby eliminating the need to impose a load on the power source. The potential difference between the toroidal coil and ground can be reduced.

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

第1図および第2図は核融合装置の従来のトロ
イダルコイルの接続方法の例を示す図、第3図は
本発明に係る核融合装置のトロイダルコイルの接
続方法の実施例の説明図、第4図は2組のトロイ
ダルコイル群を磁場の影響のない位置において直
列接続した場合の実施例の説明図、第5図および
第6図は本発明に係る核融合装置のトロイダルコ
イルの接続方法の他の実施例を示す図である。 10……放電管、12,12a,12b,12
c,12d,12e,12f,12g,12h…
…ソレノイド、16……電源、18……乱流加熱
コイル。
1 and 2 are diagrams showing an example of a conventional method for connecting toroidal coils in a fusion device, and FIG. 3 is an explanatory diagram of an embodiment of a method for connecting toroidal coils in a fusion device according to the present invention. Figure 4 is an explanatory diagram of an embodiment in which two groups of toroidal coils are connected in series at a position not affected by the magnetic field, and Figures 5 and 6 are illustrations of a method of connecting toroidal coils in a nuclear fusion device according to the present invention. It is a figure which shows another Example. 10...Discharge tube, 12, 12a, 12b, 12
c, 12d, 12e, 12f, 12g, 12h...
...Solenoid, 16...Power source, 18...Turbulent heating coil.

Claims (1)

【特許請求の範囲】 1 プラズマを閉じ込めるドーナツ状の放電管
と、この放電管内に放電管と同心状に設けたポロ
イダルコイルと、前記放電管のトロイダル方向に
沿つて設けられた複数個の前記放電管周囲のポロ
イダル方向に巻回したトロイダルコイルと、前記
放電管内に設けた前記プラズマを加熱する乱流加
熱コイルとを有する核融合装置において、前記ト
ロイダルコイルを複数の組に分割し、これらトロ
イダルコイルに電流を供給する電源を磁場の影響
を受けない位置に設けたことを特徴とする核融合
装置。 2 前記トロイダルコイルの複数の組は、磁場の
影響を受けないところにおいて直列に接続されて
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。
[Scope of Claims] 1. A donut-shaped discharge tube that confines plasma, a poloidal coil provided within the discharge tube concentrically with the discharge tube, and a plurality of the discharge tubes provided along the toroidal direction of the discharge tube. In a nuclear fusion device having a toroidal coil wound in a surrounding poloidal direction and a turbulent heating coil provided in the discharge tube for heating the plasma, the toroidal coil is divided into a plurality of groups, and the toroidal coil is divided into a plurality of groups. A nuclear fusion device characterized by having a power source that supplies current located at a location that is not affected by magnetic fields. 2. The nuclear fusion device according to claim 1, wherein the plurality of sets of toroidal coils are connected in series in a place where they are not affected by a magnetic field.
JP58045948A 1983-03-22 1983-03-22 nuclear fusion device Granted JPS59171884A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58045948A JPS59171884A (en) 1983-03-22 1983-03-22 nuclear fusion device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58045948A JPS59171884A (en) 1983-03-22 1983-03-22 nuclear fusion device

Publications (2)

Publication Number Publication Date
JPS59171884A JPS59171884A (en) 1984-09-28
JPH0126036B2 true JPH0126036B2 (en) 1989-05-22

Family

ID=12733497

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58045948A Granted JPS59171884A (en) 1983-03-22 1983-03-22 nuclear fusion device

Country Status (1)

Country Link
JP (1) JPS59171884A (en)

Also Published As

Publication number Publication date
JPS59171884A (en) 1984-09-28

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