JPS608471B2 - nuclear fusion device - Google Patents

nuclear fusion device

Info

Publication number
JPS608471B2
JPS608471B2 JP54152965A JP15296579A JPS608471B2 JP S608471 B2 JPS608471 B2 JP S608471B2 JP 54152965 A JP54152965 A JP 54152965A JP 15296579 A JP15296579 A JP 15296579A JP S608471 B2 JPS608471 B2 JP S608471B2
Authority
JP
Japan
Prior art keywords
magnetic field
toroidal magnetic
field coil
toroidal
center
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
JP54152965A
Other languages
Japanese (ja)
Other versions
JPS5676085A (en
Inventor
智一 幸田
奉素 西郷
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 JP54152965A priority Critical patent/JPS608471B2/en
Publication of JPS5676085A publication Critical patent/JPS5676085A/en
Publication of JPS608471B2 publication Critical patent/JPS608471B2/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】 本発明は核融合装置に係り、特にトーラス型核融合菱鷹
に採用されるトロイダル磁場コイルの支持を改良した核
離合装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear fusion device, and more particularly to a nuclear dissociation device with improved support for a toroidal magnetic field coil employed in a torus-type nuclear fusion Hishitaka.

一般にトーラス型核融合袋道は、第1図に示す如く、プ
ラズマを封入するトーラス状の真空容器1と、該真空容
器を取り囲み、かつ、トーラス周方向に所定間隔をもっ
て配置されプラズマ閉じ込め用の磁場を発生する複数個
のトロイダル磁場コイル2を有する。
Generally, a torus-shaped fusion bag, as shown in Fig. 1, includes a torus-shaped vacuum vessel 1 that encloses plasma, and a magnetic field that surrounds the vacuum vessel and is placed at a predetermined interval in the circumferential direction of the torus for plasma confinement. It has a plurality of toroidal magnetic field coils 2 that generate .

個々のトロイダル磁場コイル2はトーラス状に配置され
るため「通常はトーラス内側部で切欠かれ、第2図に示
す如く、切欠き部?を有するセクター型構造となる。1
億度にも達する高温、高密度プラズマを閉じ込める装置
においては、トロイダル磁場コイル2は数万ガウスの高
磁場を発生させる必要があり、そのために寸法も大型と
なり、超重量となる。
Since the individual toroidal magnetic field coils 2 are arranged in the shape of a torus, they are usually cut out on the inside of the torus, resulting in a sector-type structure with cutouts, as shown in FIG. 2.1
In a device that confines high-temperature, high-density plasma that reaches billions of degrees, the toroidal magnetic field coil 2 needs to generate a high magnetic field of several tens of thousands of Gauss, which makes it large in size and extremely heavy.

このトロイダル磁場コイル2の支持方法として、従来は
トロイダル磁場コイル2の下部2ケ所に内側脚3aと外
側脚3bとを設け、トロイダル磁場コイル2の重量を各
々の脚にほぼ均等に配分する方法をとっていた。
Conventionally, as a method of supporting this toroidal magnetic field coil 2, an inner leg 3a and an outer leg 3b are provided at two lower parts of the toroidal magnetic field coil 2, and the weight of the toroidal magnetic field coil 2 is distributed almost equally to each leg. I was taking it.

この支持のし方によると、トロイダル磁場コイル2無通
電の時は、トロイダル磁場コイル2そのものの重量を、
2つの胸3a,3bで均等に受けもち、ベース5、及び
基礎6に対しても第1図に示すように内側脚3aのベー
ス作用力f,、内側脚3aの基礎作用力f2、外側脚3
bのベース作用大X3、及び外側脚3bの基礎作用力f
4とほぼ均等な力が作用する。しかし、トロイダル磁場
コイル2に所定の通電を行うと、このトロイダル磁場コ
イル2に第1図のようなト−ラス中心方向に電磁力mを
生じ、その求心方向成分は、トロイダル磁場コイル重量
の数十倍にも達してしまうため、トロイダル磁場コイル
2は中心ブロック4に向けて押しつけられる。一方、中
心ブロック4は、通常円筒状のものを数個積み重ねたも
のを使用しているため、上下方向には拘束力はないから
、通電時のコイル発熱によりトロイダル磁場コイル2が
熱変形を生ずると、トロイダル磁場コイル2中心から脚
先端部までの2本の胸3a,3bの熱伸び菱により「
2本の脚3a,3bのうち、温度上昇の低い方が浮き上
り、トロイダル磁場コイル2の重量を片方の脚で全て支
える結果となる。特にトロイダル磁場コイル2の内側部
は切欠き部7を有するため、他の部分より電流密度が高
く温度上昇も大きい。即ちトロイダル磁場コイル2の周
方向の温度上昇分布はほぼ第3図に示す如くなる。つま
り、該図は縦軸に温度上昇t、機軸にトロイダル磁場コ
イルの周方向角度8を示しているが、切欠き部1区間に
おいて極端に温度が上昇することがわかる。このことよ
り「第4図に示す如く、内、外側脚3a,3bに熱伸び
差Gが生じ、従って、内側胸3aでトロイダル磁場コイ
ル2の重量をほとんど受け持つこととなる。このことは
、ベース5の中心部分に集中的に内、外側脚3aのベー
ス作用力L′、及び基礎作用力f2′が作用してしまう
ことでありベース5、及び基礎6に多大な力が加わって
しまい、強度上極めて不利なものとなる欠点があった。
本発明は上述の点に鑑み成されたもので、その目的とす
るところは、運転の有無に拘わらずトロイダル磁場コイ
ルを支持するベース、基礎等に力が集中することがない
ようにして強度上の問題を解決した該融合装置を提供す
るにある。
According to this method of support, when the toroidal magnetic field coil 2 is not energized, the weight of the toroidal magnetic field coil 2 itself is
The two chests 3a and 3b equally receive the force, and the base acting force f of the inner leg 3a, the basic acting force f2 of the inner leg 3a, and the outer leg 3
The base action size X3 of b and the basic action force f of the outer leg 3b
A force approximately equal to 4 is applied. However, when a predetermined current is applied to the toroidal magnetic field coil 2, an electromagnetic force m is generated in the toroidal magnetic field coil 2 in the direction of the torus center as shown in FIG. The toroidal magnetic field coil 2 is pushed toward the center block 4 because it reaches ten times as large. On the other hand, since the center block 4 is usually made by stacking several cylindrical blocks, there is no binding force in the vertical direction, so the toroidal magnetic field coil 2 is thermally deformed due to the heat generated by the coil when energized. , due to the thermal expansion of the two chests 3a and 3b from the center of the toroidal magnetic field coil 2 to the tip of the leg.
Of the two legs 3a and 3b, the one with a lower temperature rise floats up, resulting in the entire weight of the toroidal magnetic field coil 2 being supported by one leg. In particular, since the inner part of the toroidal magnetic field coil 2 has the notch part 7, the current density is higher than other parts, and the temperature rise is also large. That is, the temperature rise distribution in the circumferential direction of the toroidal magnetic field coil 2 is approximately as shown in FIG. That is, in this figure, the vertical axis shows the temperature rise t, and the axis shows the circumferential direction angle 8 of the toroidal magnetic field coil, and it can be seen that the temperature rises extremely in one section of the notch. As a result, as shown in Fig. 4, a thermal expansion difference G occurs between the inner and outer legs 3a and 3b, and therefore, the inner chest 3a bears most of the weight of the toroidal magnetic field coil 2. The base acting force L' and the basic acting force f2' of the inner and outer legs 3a act intensively on the central part of the base 5 and the base 6, resulting in a decrease in strength. However, there were drawbacks that made it extremely disadvantageous.
The present invention has been made in view of the above points, and its purpose is to prevent force from being concentrated on the base, foundation, etc. that supports the toroidal magnetic field coil regardless of whether it is in operation or not, thereby increasing the strength. An object of the present invention is to provide a fusion device that solves the above problems.

本発明は内部にプラズマを収納する真空容器を取り囲み
、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、プラズマ閉じ込め用の磁場を発生するトロイダル
磁場コイルの各々は、トーラス中心から外方に向う半径
方向外側が脚部を介してベース上に支持され、そのトー
ラス中心側が、トロイダル磁場コイルの各々の下部に該
トロイダル磁場コイルを全数組込んだ状態で組合わされ
ほぼ円柱状となる座を設け、該座を円筒リングを鉄合さ
せてトロイダル磁場コイルに働く求心力を支持する中心
ブロックに支持させ、この円筒リングの校合によって生
じる内圧でトロイダル磁場コイルを常に中心ブロックに
押し付けることにより所期の目的を達成するように成し
たものである。
In the present invention, a plurality of toroidal magnetic field coils that surround a vacuum container that stores plasma therein, are arranged at predetermined intervals in the circumferential direction of the torus, and each of the toroidal magnetic field coils that generate a magnetic field for plasma confinement is directed outward from the center of the torus. The radially outer side is supported on the base via the legs, and the center side of the torus is assembled with the lower part of each of the toroidal magnetic field coils with all the toroidal magnetic field coils assembled to form a substantially cylindrical seat, The seat is supported by a central block that supports the centripetal force acting on the toroidal magnetic field coil by ironing a cylindrical ring, and the toroidal magnetic field coil is constantly pressed against the central block by the internal pressure generated by the alignment of the cylindrical ring, thereby achieving the desired purpose. It was made to be achieved.

以下図面の実施例に基づいて本発明を説明する。The present invention will be described below based on embodiments shown in the drawings.

尚、符号は従来と同一のものは同符号を使用する。第6
図、及び第6図に本発明の一実施例を示す。
Incidentally, the same reference numerals are used for the same parts as in the past. 6th
An embodiment of the present invention is shown in FIG.

該図に示す実施例の概略構成は「従来のものと大部分が
同様であり、ここでの説明は省略する。本実施例では、
従来の内側胸をやめ、トロイダル磁場コイル2の荷重支
えは外側胸3bのみとし「かつ、トロイダル磁場コイル
2のトーラス中心側の近い所に、トロイダル磁場コイル
2を全数組込んだ時に円柱を形成するような丸形の円形
座面2aを設け、該円形座面2aに円筒リング8を接合
させている。しかも、この円筒リング8の剛性は、円形
座面2aに鉄合した時に生ずる内圧f5が、外側脚3M
こかかるすべり抗力N以上の剛性をもっている。即ち、
運転中には熱伸びで外側脚3bが外側へ伸びるが、運転
をやめた時には外側脚3bが復元するように、円筒リン
グ8の鉄合によって生ずる内圧f5でトロイダル磁場コ
イル2を常に中心ブロック4に押し付けるようにしてい
るものである。このような本実施例の横成とすることに
より、運転の有無に拘わらず、トロイダル磁場コイル2
は常に1本足で自立するので、外側脚3bl本で荷重を
受け持ち受圧面積も大きくとることができ、従って、ベ
ース5、及び基礎6への作用力も′f4′を軽減し得t
ベース5、基礎6への強度上大きな利点となる効果があ
る。
The schematic configuration of the embodiment shown in the figure is "mostly the same as the conventional one, and the explanation here will be omitted. In this embodiment,
Instead of using the conventional inner chest, the load of the toroidal magnetic field coil 2 is supported only by the outer chest 3b.In addition, when all the toroidal magnetic field coils 2 are installed near the center of the torus of the toroidal magnetic field coil 2, a cylinder is formed. A circular seat surface 2a having a round shape is provided, and a cylindrical ring 8 is joined to the circular seat surface 2a.Moreover, the rigidity of this cylindrical ring 8 is such that the internal pressure f5 generated when it is iron-fitted to the circular seat surface 2a is , outer leg 3M
It has a rigidity that exceeds the sliding resistance N. That is,
During operation, the outer legs 3b extend outward due to thermal expansion, but the toroidal magnetic field coil 2 is always connected to the center block 4 by the internal pressure f5 generated by the iron joint of the cylindrical ring 8 so that the outer legs 3b will return to their original state when the operation is stopped. It is something that is being forced upon. By using the horizontal construction of this embodiment, the toroidal magnetic field coil 2 can be operated regardless of whether it is in operation or not.
Since it always stands on its own with one leg, the load can be handled by the 3 outer legs and the pressure-receiving area can be large. Therefore, the force acting on the base 5 and the foundation 6 can be reduced by 'f4'.
This has a great effect on the strength of the base 5 and the foundation 6.

以上説明した本発明の核融合装置によれば、トロイダル
磁場コイルの各々は、トーラス中心から外方に向う半径
方向外側が脚部を介してベース上に支持され、そのトー
ラス中心側が、トロイダル磁場コイルの各々の下部に、
該トロイダル磁場コイルを全数組込んだ状態で組合わさ
れほぼ円柱状となる座を設け、該座に円筒リングを綜合
させて中心ブロックに支持させ、この円筒リングの鉄合
によって生じる内圧で常にトロイダル磁場コイルを中心
ブロックに押し付けたものであるから、外側脚が復元す
るときでも、円筒リングの嫉合によって生じる内圧でト
ロイダル磁場コイルを常に中心ブロックに押し付けてい
るため、内側ではベース、基礎等に力が集中することが
なくなるので強度上の問題を解決できるものである。
According to the nuclear fusion device of the present invention described above, each of the toroidal magnetic field coils has its radially outer side facing outward from the torus center supported on the base via the legs, and the toroidal magnetic field coil on the torus center side. At the bottom of each of the
A seat is provided in which all of the toroidal magnetic field coils are assembled into a substantially cylindrical shape, and a cylindrical ring is integrated with the seat and supported by the center block, and the internal pressure generated by the iron fitting of this cylindrical ring constantly generates a toroidal magnetic field. Since the coil is pressed against the center block, even when the outer legs are restored, the internal pressure generated by the cylindrical ring's cylindrical ring is constantly pushing the toroidal magnetic field coil against the center block, so there is no force on the base, foundation, etc. inside. This eliminates the need for concentration, which solves the problem of strength.

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

第1図は従来のトーラス型核融合装置の横断面図、第2
図は第1図のA−A断面図、第3図はトロイダル磁場コ
イルの円周方向角度における温度上昇特性図、第4図は
内外側脚に熱伸び差Gが生じたときの荷重分坦を説明す
るための第1図の右半分を示す図、第5図は本発明の一
実施例を示すトーラス型核融合装置の横断面図、第6図
は第5図のB〜B断面図である。 1…・・・真空容器、2……トロイダル磁場コイル、2
a…・・・円形座面、3a・・・・・・内側脚、3b…
…外側脚、4・・・・・・中心ブロック、5・・・・・
1ベース・6・・・…基礎、7……切欠き部、8…・・
・円筒リング。 葵J図 努2図 好3幻 弟子図 多づ図 穿る菌
Figure 1 is a cross-sectional view of a conventional torus-type fusion device, Figure 2
The figure is a sectional view taken along line A-A in Figure 1, Figure 3 is a diagram of the temperature rise characteristics of the toroidal magnetic field coil at different angles in the circumferential direction, and Figure 4 is the load distribution when a thermal expansion difference G occurs between the medial and lateral legs. FIG. 5 is a cross-sectional view of a torus-type nuclear fusion device showing an embodiment of the present invention, and FIG. 6 is a cross-sectional view taken from B to B in FIG. 5. It is. 1... Vacuum container, 2... Toroidal magnetic field coil, 2
a...Circular seat surface, 3a...Inner leg, 3b...
...Outside leg, 4...Central block, 5...
1 Base・6...Foundation, 7...Notch, 8...
・Cylindrical ring. Aoi J Zutsutomu 2 Zuko 3 Phantom Disciple Zuzuzu Penetrating Fungi

Claims (1)

【特許請求の範囲】[Claims] 1 内部にプラズマを収納する真空容器と、該真空容器
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、プラズマ閉じ込め用の磁場を発生する
トロイダル磁場コイルと、該トロイダル磁場コイルをベ
ース上に支持する脚部と、前記真空容器のほぼ中心部に
配置され、前記トロイダル磁場コイルに働く求心力を支
持する中心ブロツクとを備え核融合装置において、前記
トロイダル磁場コイルの各々は、トーラス中心から外方
に向う半径方向外側が脚部を介してベース上に支持され
、かつトーラス中心側が前記トロイダル磁場コイル各々
の下部に、該トロイダル磁場コイルを全数組込んだ状態
で組合わされてほぼ円柱状となる座を設け、該座に円筒
リングを嵌合させて前記中心ブロツクに支持し、前記円
筒リングの嵌合によって生じる内圧で前記トロイダル磁
場コイルを常に前記中心ブロツクに押し付けるようにし
たことを特徴とする核融合装置。
1 A vacuum container that stores plasma inside, a plurality of toroidal magnetic field coils that surround the vacuum container and are arranged at predetermined intervals in the circumferential direction of the torus and generate a magnetic field for plasma confinement, and a toroidal magnetic field coil that is based on the toroidal magnetic field coil. In the nuclear fusion device, each of the toroidal magnetic field coils has a leg portion that supports the toroidal magnetic field coil, and a center block that is disposed approximately at the center of the vacuum vessel and that supports the centripetal force acting on the toroidal magnetic field coil. The radially outer side facing outward is supported on the base via the legs, and the toroidal center side is assembled to the lower part of each of the toroidal magnetic field coils with all the toroidal magnetic field coils incorporated, so that the toroidal magnetic field coil is assembled into a substantially cylindrical shape. A cylindrical ring is fitted into the seat and supported by the center block, and the toroidal magnetic field coil is constantly pressed against the center block by internal pressure generated by the fitting of the cylindrical ring. nuclear fusion device.
JP54152965A 1979-11-28 1979-11-28 nuclear fusion device Expired JPS608471B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP54152965A JPS608471B2 (en) 1979-11-28 1979-11-28 nuclear fusion device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP54152965A JPS608471B2 (en) 1979-11-28 1979-11-28 nuclear fusion device

Publications (2)

Publication Number Publication Date
JPS5676085A JPS5676085A (en) 1981-06-23
JPS608471B2 true JPS608471B2 (en) 1985-03-02

Family

ID=15552020

Family Applications (1)

Application Number Title Priority Date Filing Date
JP54152965A Expired JPS608471B2 (en) 1979-11-28 1979-11-28 nuclear fusion device

Country Status (1)

Country Link
JP (1) JPS608471B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6284688U (en) * 1985-11-18 1987-05-29

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6284688U (en) * 1985-11-18 1987-05-29

Also Published As

Publication number Publication date
JPS5676085A (en) 1981-06-23

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