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JPS6244629B2 - - Google Patents
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JPS6244629B2 - - Google Patents

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Publication number
JPS6244629B2
JPS6244629B2 JP54122031A JP12203179A JPS6244629B2 JP S6244629 B2 JPS6244629 B2 JP S6244629B2 JP 54122031 A JP54122031 A JP 54122031A JP 12203179 A JP12203179 A JP 12203179A JP S6244629 B2 JPS6244629 B2 JP S6244629B2
Authority
JP
Japan
Prior art keywords
torus
magnetic field
vacuum
vacuum container
electromagnetic force
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
JP54122031A
Other languages
Japanese (ja)
Other versions
JPS5646486A (en
Inventor
Fumio Iida
Juji Okumura
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 JP12203179A priority Critical patent/JPS5646486A/en
Publication of JPS5646486A publication Critical patent/JPS5646486A/en
Publication of JPS6244629B2 publication Critical patent/JPS6244629B2/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)
  • Containers, Films, And Cooling For Superconductive Devices (AREA)

Description

【発明の詳細な説明】 本発明はトーラス形核融合装置に係り、特に、
超電導トロイダル磁場コイルを備えているものに
好適なトーラス形核融合装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a torus-shaped nuclear fusion device, and in particular,
The present invention relates to a torus-shaped fusion device suitable for those equipped with superconducting toroidal magnetic field coils.

従来、トーラス形核融合装置の超電導トロイダ
ル磁場コイルの構成は、第2図に示すようにヘリ
ウム容器2に収納され、液体ヘリウム、または超
臨界ヘリウム等の冷媒によつて冷却されるように
構成され、さらに、第2図に示すように輻射熱を
遮蔽する輻射シールド3(液体窯素により冷
却)、真空断熱のための真空容器4、及びスペー
サ5により囲まれている。
Conventionally, the configuration of a superconducting toroidal magnetic field coil in a torus-shaped fusion device is such that it is housed in a helium container 2 and cooled by a coolant such as liquid helium or supercritical helium, as shown in FIG. Furthermore, as shown in FIG. 2, it is surrounded by a radiation shield 3 (cooled by liquid silicon) for shielding radiant heat, a vacuum container 4 for vacuum insulation, and a spacer 5.

このように構成される超電導トロイダル磁場コ
イル1が、第1図に示す如く、トーラス状のプラ
ズマ放電管9を取り囲み、かつ、トーラス方向に
所定間隔をもつて複数個配置されている。そし
て、トーラス中心位置には中心支柱7、超電導ト
ロイダル磁場コイル1のトーラス内、外周側にお
ける相隣接する超電導トロイダル磁場コイル1間
には、それぞれ電磁力サポート6が配置され、ト
ーラス形核融合装置が構成される。
As shown in FIG. 1, a plurality of superconducting toroidal magnetic field coils 1 configured as described above surround a toroidal plasma discharge tube 9 and are arranged at predetermined intervals in the toroidal direction. A central support 7 is placed at the center of the torus, an electromagnetic force support 6 is placed inside the torus of the superconducting toroidal magnetic field coil 1, and an electromagnetic force support 6 is placed between adjacent superconducting toroidal magnetic field coils 1 on the outer periphery. configured.

しかして、このような構成において、超電導ト
ロイダル磁場コイル1を励磁した際に生じる電磁
力は、ヘリウム容器2、スペーサ5、および真空
容器4をそれぞれ介して、室温の電磁力サポート
6、および中心支柱7により支持される。したが
つて、室温の電磁力サポート6、および中心支柱
7から超電導トロイダル磁場コイル1に流入する
熱負荷は、超電導トロイダル磁場コイル1が大形
化して電磁力が大きくなればなるほど増大するこ
とになり、強力な冷凍液化装置等が必要となつて
くる。
In such a configuration, the electromagnetic force generated when the superconducting toroidal magnetic field coil 1 is excited is transmitted to the electromagnetic force support 6 at room temperature and the center column via the helium container 2, the spacer 5, and the vacuum container 4, respectively. Supported by 7. Therefore, the heat load flowing into the superconducting toroidal magnetic field coil 1 from the electromagnetic force support 6 and the center column 7 at room temperature increases as the superconducting toroidal magnetic field coil 1 becomes larger and the electromagnetic force becomes larger. , powerful refrigeration and liquefaction equipment will be required.

本発明は上述の点鑑み成されたもので、その目
的とするところは、超電導トロイダル磁場コイル
が大形化しても、それに流入する熱負荷を小さく
抑えることができ、強力な冷凍液化装置等を必要
としないトーラス形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 purpose is to be able to suppress the heat load flowing into the superconducting toroidal magnetic field coil to a small level even when the superconducting toroidal magnetic field coil becomes large in size. To provide a torus-shaped fusion device that does not require

本発明は内部にプラズマを収納するトーラス状
のプラズマ放電管を取り囲み、かつ、トーラス方
向に所定間隔をもつて複数個配置され、ヘリウム
容器に収納された超電導トロイダル磁場コイルの
相隣接する少なくとも2個を単一の真空な容器に
収納してモジユール化してトーラス状中心に対し
て放射状に配置すると共に、各モジユールの真空
な容器をトーラス中心に配置された真空容器に接
合固定して真空保持が可能な一体の真空容器と
し、かつ、このモジユール化された部分間に位置
する電磁力サポートを、相隣接する単一の真空な
容器を連通するために設けられた輻射シールドが
施された真空配管内に設置されて低温状態に維持
されていることにより、所期の目的を達成するよ
うになしたものである。
The present invention includes at least two adjacent superconducting toroidal magnetic field coils that surround a toroidal plasma discharge tube that houses plasma therein, are arranged at predetermined intervals in the direction of the torus, and are housed in a helium container. is housed in a single vacuum container, made into modules, and arranged radially around the center of the torus, and the vacuum container of each module is bonded and fixed to the vacuum container placed at the center of the torus to maintain vacuum. The electromagnetic force support located between the modularized parts is placed in a vacuum piping provided with a radiation shield to connect the adjacent single vacuum vessels. It was designed to achieve its intended purpose by being installed at a low temperature and maintained at a low temperature.

以下、図面の実施例基づいて本発明を説明す
る。尚、符号は従来と同一のものは同符号を使用
する。
The present invention will be explained below based on the embodiments shown in the drawings. Incidentally, the same reference numerals are used for the same parts as in the past.

第3図、及び第4図に本発明の一実施例を示
す。該図の如く、ヘリウム容器2に収納された超
電導トロイダル磁場コイル1の相隣接する少なく
とも2個を単一の真空な容器24収納してモジユ
ール化する。このモジユールをトーラス中心に配
置された真空容器14に対して放射状に配置し、
モジユールの真空な容器24とトーラス中心に配
置されている真空容器14とを溶接接合すること
により一体の真空容器を形成し、真空保持が可能
となつている。そして、超電導トロイダル磁場コ
イル1のトーラス内周側は、第3図に示すように
相互に張り合い構造となつて真空容器14,24
で囲われていると共に、トーラス外周側は、真空
配管8によつて内包されている電磁力サポート6
によつて相互に連結されている。このように構成
された超電導トロイダル磁場コイル1、およびヘ
リウム容器2は、本実施例では第3図に示すよう
に、相隣接する2つが1組となつて真空な容器2
4内に収納されモジユール化されており、この真
空な容器24は、超電導トロイダル磁場コイル1
と同様真空容器14に放射状に配置されて接合さ
れ真空容器14と一体の真空容器が形成され、そ
のトーラス外周側は、電磁力サポート6を内包す
る真空容器8によつて互に接続されている。そし
て、真空な容器24、および真空配管8の内面に
は、第3図に示すように輻射シールド3がそれぞ
れ配置されている。
An embodiment of the present invention is shown in FIGS. 3 and 4. As shown in the figure, at least two adjacent superconducting toroidal magnetic field coils 1 housed in a helium vessel 2 are housed in a single vacuum vessel 24 to form a module. This module is arranged radially with respect to the vacuum container 14 arranged at the center of the torus,
By welding and joining the vacuum container 24 of the module and the vacuum container 14 placed at the center of the torus, an integrated vacuum container is formed and vacuum maintenance is possible. The inner circumferential side of the torus of the superconducting toroidal magnetic field coil 1 has a structure in which it is stuck to each other as shown in FIG.
At the same time, the outer peripheral side of the torus is surrounded by an electromagnetic force support 6 enclosed by a vacuum pipe 8.
are interconnected by. In this embodiment, as shown in FIG. 3, the superconducting toroidal magnetic field coil 1 and the helium container 2 configured in this manner are assembled into a vacuum container 2 in which two adjacent ones form a set.
This vacuum container 24 houses the superconducting toroidal magnetic field coil 1.
Similarly, they are arranged radially and joined to the vacuum vessel 14 to form a vacuum vessel integrated with the vacuum vessel 14, and the outer peripheral side of the torus is connected to each other by the vacuum vessel 8 containing the electromagnetic force support 6. . Radiation shields 3 are arranged on the inner surfaces of the vacuum container 24 and the vacuum piping 8, respectively, as shown in FIG.

このような構成において、コイル励磁時に生じ
るトーラス中心に向く電磁力(中心力)は、相互
に張り合い構造となつているヘリウム容器2のト
ーラス内周側で支持され、また、電磁力(転倒
力)の支持は、電磁力サポート6によつて行なわ
れる。この電磁力サポート6は、真空容器24、
真空配管8、および輻射シールド3により包囲さ
れているので低温支持方式となつている。
In such a configuration, the electromagnetic force (central force) directed toward the center of the torus generated when the coil is excited is supported by the inner circumferential side of the torus of the helium container 2, which has a mutually tensioned structure, and the electromagnetic force (overturning force) The support is provided by an electromagnetic force support 6. This electromagnetic force support 6 includes a vacuum container 24,
Since it is surrounded by the vacuum piping 8 and the radiation shield 3, it is a low-temperature support system.

従つて、本実施例の構成とすることにより超電
導トロイダル磁場コイル1が大形化しても、コイ
ル励磁時に生じるトーラス中心に向く電磁力(中
心力)に対して、超電導トロイダル磁場コイル1
は室温のサポートなしに直接ヘリウム容器2間で
支持されているので、従来の室温支持方式と異な
りサポートからの侵入熱を完全に遮断することが
できる。また、電磁力(転倒力)に対しては、従
来と同様電磁力サポート6で支持されているが、
真空容器24、真空配管8、および輻射シールド
3によつて低温支持方式となつているので、電磁
力サポート6からの侵入熱を大巾に減少させるこ
とができる。更に、超電導トロイダル磁場コイル
1の相隣接する少なくとも2個を単一な真空な空
器24に収納してモジユール化することにより、
全ての超電導トロイダル磁場コイルを含むような
大きな真空容器は不要となり、装置をコンパクト
化する上で有効であると共に、プラズマ放電管へ
のアクセスが真空容器を通さず、大気中から直接
できるので、加熱計測ポートの取付等がより簡単
であるという効果もある。
Therefore, even if the size of the superconducting toroidal magnetic field coil 1 is increased by adopting the configuration of this embodiment, the superconducting toroidal magnetic field coil 1 will be able to withstand the electromagnetic force (central force) directed toward the torus center generated during coil excitation.
Since it is directly supported between the helium containers 2 without any support at room temperature, it is possible to completely block out heat intrusion from the support, unlike the conventional room temperature support system. In addition, the electromagnetic force (falling force) is supported by the electromagnetic force support 6 as before, but
Since the vacuum container 24, the vacuum piping 8, and the radiation shield 3 provide a low-temperature support system, the intrusion heat from the electromagnetic force support 6 can be greatly reduced. Furthermore, by housing at least two adjacent superconducting toroidal magnetic field coils 1 in a single vacuum chamber 24 to form a module,
A large vacuum vessel containing all the superconducting toroidal magnetic field coils is no longer required, which is effective in making the device more compact, and the plasma discharge tube can be accessed directly from the atmosphere without passing through the vacuum vessel, allowing heating. There is also the effect that installation of the measurement port is easier.

以上説明した本発明のトーラス形核融合装置に
よれば、内部にプラズマを収納するトーラス状の
プラズマ放電管を取り囲み、かつ、トーラス方向
に所定間隔をもつて複数個配置され、ヘリウム容
器に収納された超電導トロイダル磁場コイルの相
隣接する少なくとも2個を単一の真空な容器に収
納してモジユール化してトーラス中心に対して放
射状に配置すると共に、各モジユールの真空な容
器をトーラス中心に配置された真空容器に接合固
定して真空保持が可能な一体の真空容器とし、か
つ、このモジユール化された部分間に位置する電
磁力サポートを、相隣接する単一の真空な容器を
連通するために設けられた輻射シールドが施され
た真空配管内に設置されて低温状態に維持されて
いるものであるから、超電導トロイダル磁場コイ
ルが大形化しても、コイル励磁時に生じるトーラ
ス中心方向に作用する電磁力に対しては直接ヘリ
ウム容器間で支持でき、また、トーラス外周側で
働く電磁力に対しては、低温状態に維持されてい
る電磁力サポートで支持できるため、それに流入
する熱負荷を小さく抑えることができ、特に強力
な冷凍液化装置等を必要としないので、此種トー
ラス形核融合装置には非常に有効である。
According to the torus-shaped fusion device of the present invention described above, a plurality of plasma discharge tubes are arranged at predetermined intervals in the direction of the torus, surrounding a toroidal plasma discharge tube that stores plasma inside, and are housed in a helium container. At least two adjacent superconducting toroidal magnetic field coils are housed in a single vacuum container to form a module and arranged radially with respect to the center of the torus, and the vacuum container of each module is arranged at the center of the torus. An integrated vacuum container that can be bonded and fixed to a vacuum container to maintain a vacuum, and an electromagnetic force support located between the modular parts is provided to connect adjacent single vacuum containers. Since the superconducting toroidal magnetic field coil is installed in a vacuum pipe with a radiation shield and maintained at a low temperature, even if the superconducting toroidal magnetic field coil becomes larger, the electromagnetic force that is generated when the coil is excited and acts toward the center of the torus will be reduced. The torus can be supported directly between the helium containers, and the electromagnetic force acting on the outer circumference of the torus can be supported by an electromagnetic force support that is maintained at a low temperature, so the heat load flowing into it can be kept small. This method is very effective for this type of torus-shaped fusion device because it does not require a particularly powerful freezing and liquefaction device.

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

第1図は従来のトーラス形核融合装置の一部を
示す水平断面図、第2図は第1図の超電導トロイ
ダル磁場コイル近傍を拡大して示す断面図、第3
図は本発明のトーラス形核融合装置の一実施例の
一部を示す水平断面図、第4図は第3図の要部分
解斜視図である。 1……超電導トロイダル磁場コイル、2……ヘ
リウム容器、3……輻射シールド、6……電磁力
サポート、8……真空配管、9……プラズマ放電
管、14,24……真空容器。
Figure 1 is a horizontal cross-sectional view showing a part of a conventional toroidal fusion device, Figure 2 is an enlarged cross-sectional view of the vicinity of the superconducting toroidal magnetic field coil in Figure 1, and Figure 3 is a cross-sectional view showing a portion of a conventional toroidal fusion device.
The figure is a horizontal sectional view showing a part of an embodiment of the torus-shaped nuclear fusion device of the present invention, and FIG. 4 is an exploded perspective view of the main part of FIG. 3. 1... Superconducting toroidal magnetic field coil, 2... Helium container, 3... Radiation shield, 6... Electromagnetic force support, 8... Vacuum piping, 9... Plasma discharge tube, 14, 24... Vacuum container.

Claims (1)

【特許請求の範囲】[Claims] 1 内部にプラズマを収納するトーラス状のプラ
ズマ放電管と、該プラズマ放電管を取り囲み、か
つ、トーラス方向に所定間隔をもつて複数個配置
され、ヘリウム容器に収納された超電導トロイダ
ル磁場コイルと、該超電導トロイダル磁場コイル
トーラス外周側の各々のトーラス方向間に介在さ
れた電磁力サポートとを備えたトーラス形核融合
装置において、前記超電導トロイダル磁場コイル
の相隣接する少なくとも2個を単一の真空な容器
に収納してモジユール化してトーラス中心に対し
て放射状に配置すると共に、各モジユールの真空
な容器をトーラス中心に配置された真空容器に接
合固定して真空保持が可能な一体の真空容器と
し、かつ、このモジユール化された部分間に位置
する前記電磁力サポートを、相隣接する単一の真
空な容器を連通するために設けられ輻射シールド
が施された真空配管内に設置されて低温状態に維
持されていることを特徴とするトーラス形核融合
装置。
1. A toroidal plasma discharge tube that stores plasma therein, a plurality of superconducting toroidal magnetic field coils surrounding the plasma discharge tube, arranged at predetermined intervals in the direction of the torus, and housed in a helium container; In a toroidal fusion device comprising a superconducting toroidal magnetic field coil and an electromagnetic force support interposed between each torus direction on the outer circumferential side of the torus, at least two adjacent superconducting toroidal magnetic field coils are arranged in a single vacuum container. The vacuum container of each module is connected and fixed to the vacuum container arranged at the center of the torus to form an integrated vacuum container capable of maintaining vacuum, and , the electromagnetic force support located between the modularized parts is maintained at a low temperature by being installed in a vacuum piping provided with a radiation shield and provided to communicate a single vacuum container adjacent to each other. A torus-shaped fusion device characterized by:
JP12203179A 1979-09-25 1979-09-25 Nuclear fusion device Granted JPS5646486A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP12203179A JPS5646486A (en) 1979-09-25 1979-09-25 Nuclear fusion device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP12203179A JPS5646486A (en) 1979-09-25 1979-09-25 Nuclear fusion device

Publications (2)

Publication Number Publication Date
JPS5646486A JPS5646486A (en) 1981-04-27
JPS6244629B2 true JPS6244629B2 (en) 1987-09-21

Family

ID=14825873

Family Applications (1)

Application Number Title Priority Date Filing Date
JP12203179A Granted JPS5646486A (en) 1979-09-25 1979-09-25 Nuclear fusion device

Country Status (1)

Country Link
JP (1) JPS5646486A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5364356B2 (en) * 2008-12-11 2013-12-11 三菱重工業株式会社 Superconducting coil device
JP6605324B2 (en) 2015-12-24 2019-11-13 川崎重工業株式会社 Swing arm support structure

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5388498A (en) * 1977-01-17 1978-08-03 Hitachi Ltd Torus type nuclear fusion device

Also Published As

Publication number Publication date
JPS5646486A (en) 1981-04-27

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