JPS6046670B2 - nuclear fusion device - Google Patents

nuclear fusion device

Info

Publication number
JPS6046670B2
JPS6046670B2 JP53033731A JP3373178A JPS6046670B2 JP S6046670 B2 JPS6046670 B2 JP S6046670B2 JP 53033731 A JP53033731 A JP 53033731A JP 3373178 A JP3373178 A JP 3373178A JP S6046670 B2 JPS6046670 B2 JP S6046670B2
Authority
JP
Japan
Prior art keywords
toroidal coil
nuclear fusion
fusion device
coil
center pole
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
JP53033731A
Other languages
Japanese (ja)
Other versions
JPS54125398A (en
Inventor
貞夫 宮内
幸男 青木
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.)
Mitsubishi Electric Corp
Original Assignee
Mitsubishi Electric Corp
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 Mitsubishi Electric Corp filed Critical Mitsubishi Electric Corp
Priority to JP53033731A priority Critical patent/JPS6046670B2/en
Publication of JPS54125398A publication Critical patent/JPS54125398A/en
Publication of JPS6046670B2 publication Critical patent/JPS6046670B2/en
Expired 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

Description

【発明の詳細な説明】 この発明は一般に核融合装置に関し、より詳しくはトカ
マク形核融合装置に用いられるディスク形のトロイダル
コイルに関するものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates generally to nuclear fusion devices, and more particularly to a disk-shaped toroidal coil used in a tokamak-type nuclear fusion device.

従来この種のトロイダルコイルを備えた核融合装置は、
第1図および第2図に示されるように構成されていた。
符号1は、センターポールで、このセンターポール1に
接してトロイダルコイル2が設けられている。
Conventional fusion devices equipped with this type of toroidal coil are
It was constructed as shown in FIGS. 1 and 2.
Reference numeral 1 denotes a center pole, and a toroidal coil 2 is provided in contact with the center pole 1.

トロイダルコイル2は、第5図A部のように複数個の素
線3とキヤン5とからなり、真空容器2aを取巻くよう
に配設されている。トロイダルコイル2に直流を流すと
、コイルの囲むドーナツ状空間に磁場が発生し、真空容
器2a内のプラズマ位置を安定させる。
The toroidal coil 2 is made up of a plurality of wires 3 and cans 5, as shown in part A of FIG. 5, and is arranged so as to surround the vacuum vessel 2a. When a direct current is passed through the toroidal coil 2, a magnetic field is generated in the donut-shaped space surrounded by the coil, and the plasma position within the vacuum vessel 2a is stabilized.

他方、この磁場と電流の相互作用によつて、トロイダル
コイル2には、内部から外部に向かう磁気圧力が作用す
る。
On the other hand, due to the interaction between the magnetic field and the current, magnetic pressure acts on the toroidal coil 2 from the inside to the outside.

この磁気圧力は、センターポール1の中心からの距離に
反比例して大きくなるために絶縁部に加わる圧縮力もセ
ンターポール1との接触面PQ付近が最大になる欠点が
ある。絶縁物に加えられる圧縮力をPQの方向に均等化
すると、局部的な最大圧縮応力を無くすることができる
。この方法の一例として、センターポールの支持構造を
PQ方向に変化させて、バネ定数を加減する方法が従来
採用されていた。しかし、この方法は、工作上相当に複
雑で困難な点を含んでいる上に、総合的な求心力が一定
である以上、応力を一定値以下にすることは不可能であ
る。この発明は、電磁力による総合求心力を減少させる
とともにセンターポールの支持バネ常数を一定値に近く
とることによつて、絶縁物に加わる圧縮応力を低下せ、
通常の絶縁方式で足りるトロイダルコイルを備えた核融
合装置を提供することを’目的とするものである。以下
、この発明の一実施例を図面に基いて詳細に説明する。
第3図〜第6図は、この発明の実施例を示すものである
Since this magnetic pressure increases in inverse proportion to the distance from the center of the center pole 1, there is a drawback that the compressive force applied to the insulating portion is greatest near the contact surface PQ with the center pole 1. By equalizing the compressive force applied to the insulator in the direction of PQ, the local maximum compressive stress can be eliminated. As an example of this method, a method has conventionally been adopted in which the support structure of the center pole is changed in the PQ direction to adjust the spring constant. However, this method is quite complicated and difficult to work with, and as long as the overall centripetal force is constant, it is impossible to reduce the stress below a certain value. This invention reduces the compressive stress applied to the insulator by reducing the total centripetal force due to electromagnetic force and keeping the support spring constant of the center pole close to a constant value.
The purpose of this invention is to provide a nuclear fusion device equipped with a toroidal coil that requires ordinary insulation. Hereinafter, one embodiment of the present invention will be described in detail based on the drawings.
3 to 6 show embodiments of this invention.

1は、センターポール、2は、トロイダルコイル、3は
、トロイダルコイルの素線、4は、素線3間および素線
3とキヤン5間の絶縁材、6,7は、キヤン5と一体の
支持片である。
1 is a center pole, 2 is a toroidal coil, 3 is a strand of the toroidal coil, 4 is an insulating material between the strands 3 and between the strands 3 and the can 5, 6 and 7 are integral with the can 5 It is a support piece.

10は、支持部材で、その一端は上記支持片6および7
とピン8により回動可能に連結されている。
10 is a support member, one end of which is connected to the support pieces 6 and 7.
and are rotatably connected by a pin 8.

支持部材10の他端には、その両側に、ピン9によつて
軸支されたプーリ11および12が設けられ、プーリ1
1および12には、ローブ13および14が係合されて
いる。第4図において、トロイダルコイル2に直流を流
すと、コイル2で囲むドーナツ状の空間に磁場が発生し
、真空容器2a内のプラズマ位置を安定させる。
At the other end of the support member 10, pulleys 11 and 12 are provided on both sides, which are pivotally supported by a pin 9.
1 and 12 are engaged with lobes 13 and 14. In FIG. 4, when a direct current is passed through the toroidal coil 2, a magnetic field is generated in a donut-shaped space surrounded by the coil 2, and the plasma position within the vacuum vessel 2a is stabilized.

センターボール1向きの電磁求心力は、コイル2の形状
、寸法により決定される一定値であるので、接触頂アQ
での絶縁応力を減少させるためには、上記求心力とは逆
方向の力(遠心力)をトロイダルコイル2の一部に加え
ればよい。上記絶縁応力は、トロイダルコイル2を形成
している素線3とキヤン5との間の伝達力によるもので
あるため、素線3の曲げ剛性が大きい場合すなわち第5
図にて図示するごとく素線3における前記トロイダルコ
イル2の半径方向に沿つた長さ士bが該コイル2の周方
向に沿つた長さaに比較して大きくb/a〉1の関係が
成立するような場合にこの発明の一実施例によるローブ
13,14のごとき荷重付与部材を設けた構成は特に有
効である。又、前記トロイダルコイル2は、温度上昇に
よつて上下、左右に熱膨張を起すので遠心力の与え方と
しては、できるだけバネ定数の小さなものが良く、この
点からも前記ローブ13,14を設けた構成は有効であ
る。なお、上記では、キヤン5は一体のものとして構成
したが、これは第6図のように分割構成とすることもで
きる。
Since the electromagnetic centripetal force directed toward the center ball 1 is a constant value determined by the shape and dimensions of the coil 2, the contact apex Q
In order to reduce the insulation stress in the toroidal coil 2, a force (centrifugal force) in the opposite direction to the centripetal force described above may be applied to a part of the toroidal coil 2. The above-mentioned insulation stress is due to the transmission force between the wire 3 forming the toroidal coil 2 and the can 5. Therefore, when the bending rigidity of the wire 3 is large, that is, the fifth
As shown in the figure, the length b of the wire 3 along the radial direction of the toroidal coil 2 is larger than the length a of the coil 2 along the circumferential direction, and the relationship b/a>1 is established. In such cases, a configuration in which load applying members such as lobes 13 and 14 according to an embodiment of the present invention are provided is particularly effective. Further, since the toroidal coil 2 undergoes thermal expansion vertically and horizontally due to temperature rise, it is best to use a coil with a spring constant as small as possible in order to apply centrifugal force, and from this point of view as well, the lobes 13 and 14 are provided. The configured configuration is valid. In the above, the can 5 is configured as an integral unit, but it can also be configured as a divided unit as shown in FIG.

以上のようにこの発明によれば、トロイダルコイルの他
側に、センタボール側とは逆方向の荷重を前記トロイダ
ルに付与する荷重付与部を設けることとしたので、絶縁
物に加わる圧縮応力を低下させ、通常の絶縁方式で足り
るトロイダルコイルを備えた核融合装置が得られる効果
がある。
As described above, according to the present invention, a load applying portion is provided on the other side of the toroidal coil for applying a load to the toroid in the direction opposite to that on the center ball side, thereby reducing compressive stress applied to the insulator. This has the effect of providing a nuclear fusion device equipped with a toroidal coil for which a normal insulation method is sufficient.

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

第1図は、従来のトロイダルコイルを備た核融合装置の
構成を示す平面図、第2図は、同要部の断面図、第3図
は、この発明の一実施例の第1図と同様の状態の平面図
、第4図は、その要部の断面図、第5図は、第4図のA
−A線断面図、第6図は、この発明の他の変形例である
。 1・・・・・・センターボール、2・・・・・・トロイ
ダルコイル、2a・・・・・・真空容器、3・・・・・
・トロイダルコイルの素線、5・・・・・キヤン、6,
7・・・・・・支持片、10・・・支持部材、11,1
2・・・・・・プーリ、13,14・・・・・・ローブ
FIG. 1 is a plan view showing the configuration of a conventional nuclear fusion device equipped with a toroidal coil, FIG. 2 is a cross-sectional view of the same essential parts, and FIG. A plan view of the same state, FIG. 4 is a sectional view of the main part, and FIG. 5 is A of FIG.
The sectional view taken along line -A in FIG. 6 shows another modification of the present invention. 1... Center ball, 2... Toroidal coil, 2a... Vacuum container, 3...
・Toroidal coil wire, 5...Kyan, 6,
7...Support piece, 10...Support member, 11,1
2...Pulley, 13,14...Lobe.

Claims (1)

【特許請求の範囲】 1 一側がセンタポールに取り付けられるとともに、該
センタポールに対して放射状に配設されたトロイダルコ
イルを有する核融合装置において、前記トロイダルコイ
ルの他側に、前記センタポール側とは逆方向の荷重を前
記トロイダルコイルに付与する荷重付与部を設けたこと
を特徴とする核融合装置。 2 前記荷重付与部は、ロープで構成されていることを
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. In a nuclear fusion device having a toroidal coil attached to a center pole on one side and arranged radially with respect to the center pole, the other side of the toroidal coil is attached to the center pole side. A nuclear fusion device characterized in that a load applying section is provided that applies a load in an opposite direction to the toroidal coil. 2. The nuclear fusion device according to claim 1, wherein the load applying section is composed of a rope.
JP53033731A 1978-03-23 1978-03-23 nuclear fusion device Expired JPS6046670B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP53033731A JPS6046670B2 (en) 1978-03-23 1978-03-23 nuclear fusion device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP53033731A JPS6046670B2 (en) 1978-03-23 1978-03-23 nuclear fusion device

Publications (2)

Publication Number Publication Date
JPS54125398A JPS54125398A (en) 1979-09-28
JPS6046670B2 true JPS6046670B2 (en) 1985-10-17

Family

ID=12394539

Family Applications (1)

Application Number Title Priority Date Filing Date
JP53033731A Expired JPS6046670B2 (en) 1978-03-23 1978-03-23 nuclear fusion device

Country Status (1)

Country Link
JP (1) JPS6046670B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6328263U (en) * 1986-08-11 1988-02-24

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6328263U (en) * 1986-08-11 1988-02-24

Also Published As

Publication number Publication date
JPS54125398A (en) 1979-09-28

Similar Documents

Publication Publication Date Title
KR20030087035A (en) Stator of rotating electric motor
JPS6046670B2 (en) nuclear fusion device
JPH0475642B2 (en)
JP3549295B2 (en) Superconducting cable
JPS6193604A (en) Superconducting magnet
JPH0326621Y2 (en)
JP2883071B1 (en) Superconducting field winding conductor
JPS62169405A (en) Manufacture of superconducting coil
JP3362973B2 (en) Winding rotor coil
JPH0877831A (en) Overhead power transmission line
JPS6049268B2 (en) Toroidal winding of fusion device
JP2685367B2 (en) Superconducting conductor
JPH04142707A (en) Superconducting coil
JPS6328564Y2 (en)
JPH1186922A (en) Connecting part structure for superconducting cable
JPH0341446Y2 (en)
JPS60219712A (en) Manufacture of compound superconductive coil
JPH02288110A (en) Superconducting conductor
JPH087673A (en) Oxide superconductor
JPS59198868A (en) Rotor of superconductive rotary electric machine
JPS61159715A (en) Balun coil
JPH04125041A (en) Field winding for strand-wound salient pole type synchronous machine
JPH031507A (en) Superconducting magnet
JPH01170345A (en) Armature for motor
JPH02228235A (en) Stator of induction motor