JPH0472199B2 - - Google Patents
Info
- Publication number
- JPH0472199B2 JPH0472199B2 JP58188302A JP18830283A JPH0472199B2 JP H0472199 B2 JPH0472199 B2 JP H0472199B2 JP 58188302 A JP58188302 A JP 58188302A JP 18830283 A JP18830283 A JP 18830283A JP H0472199 B2 JPH0472199 B2 JP H0472199B2
- Authority
- JP
- Japan
- Prior art keywords
- magnetic field
- plasma
- field coil
- thermal radiation
- superconducting
- 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 - Lifetime
Links
- 230000005855 radiation Effects 0.000 claims description 23
- 230000004927 fusion Effects 0.000 claims description 9
- 239000000463 material Substances 0.000 claims description 4
- 239000000615 nonconductor Substances 0.000 claims description 2
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 2
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 2
- 229910052782 aluminium Inorganic materials 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 229910052802 copper Inorganic materials 0.000 description 2
- 239000010949 copper Substances 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 230000000694 effects Effects 0.000 description 1
- 239000012777 electrically insulating material Substances 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- 230000000087 stabilizing effect Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229920003002 synthetic resin Polymers 0.000 description 1
- 239000000057 synthetic resin Substances 0.000 description 1
- 230000003313 weakening effect Effects 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/10—Nuclear fusion reactors
Landscapes
- Plasma Technology (AREA)
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明はプラズマ容器内にプラズマを閉じ込め
るトロイダル磁場コイルを超電導コイルで構成す
るようにしたトーラス形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 torus-shaped nuclear fusion device in which a toroidal magnetic field coil for confining plasma within a plasma vessel is constructed of a superconducting coil.
第１図は従来のトーラス形核融合装置の縦断面
図である。超高温のプラズマ１を閉じ込める円環
状のプラズマ容器２は、その内部が高真空状態に
保持されている。このプラズマ容器２の外周に
は、プラズマ閉じ込め用の磁場を発生する複数個
の常電導コイルからなるトロイダル磁場コイル３
が、等間隔で、全体としてトーラス状となるよう
に配置されている。これらのトロイダル磁場コイ
ル３は上ベース４と下ベース５とによつて支持さ
れ、またプラズマ制御用の垂直磁場を発生する内
部ポロイダル磁場コイル６および外部ポロイダル
磁場コイル７は、プラズマ容器２とトロイダル磁
場コイル３との間、および架構８の上下にそれぞ
れ配置されている。また、プラズマ容器２内に閉
じ込められたプラズマ１を加熱するための変流器
コイル９は中央主柱１０の周りに装着されてい
る。
FIG. 1 is a longitudinal sectional view of a conventional toroidal fusion device. An annular plasma container 2 that confines ultra-high temperature plasma 1 is maintained in a high vacuum state inside. At the outer periphery of the plasma container 2, a toroidal magnetic field coil 3 consisting of a plurality of normally conducting coils generates a magnetic field for plasma confinement.
are arranged at equal intervals so as to form a torus shape as a whole. These toroidal magnetic field coils 3 are supported by an upper base 4 and a lower base 5, and an internal poloidal magnetic field coil 6 and an external poloidal magnetic field coil 7 that generate a vertical magnetic field for plasma control are connected to the plasma vessel 2 and the toroidal magnetic field. They are arranged between the coil 3 and above and below the frame 8, respectively. Further, a current transformer coil 9 for heating the plasma 1 confined within the plasma container 2 is mounted around the central main column 10.
このようにトーラス形核融合装置においては、
そのトロイダル磁場コイルとして、従来は常電導
コイルが用いられていたが、発生させるべきトロ
イダル磁場の増強と使用電力量低減の観点から、
最近超電導コイルの使用が望まれている。 In this way, in a torus-shaped fusion device,
Conventionally, a normal conducting coil was used as the toroidal magnetic field coil, but from the viewpoint of increasing the toroidal magnetic field to be generated and reducing the amount of power used,
Recently, the use of superconducting coils has been desired.
ところで、トーラス形核融合装置では前記トロ
イダル磁場コイルと共にプラズマ容器内のプラズ
マを制御するポロイダル磁場コイルの設置が不可
欠である。 Incidentally, in a toroidal fusion device, it is essential to install a poloidal magnetic field coil for controlling the plasma in the plasma container together with the toroidal magnetic field coil.
しかしながら、トロイダル磁場コイルを超電導
形にした場合、この超電導コイルは極低温（4.2
〓）であり、またポロイダル磁場コイルは常温で
あり、更に高真空状態に維持されたプラズマ容器
内のプラズマは超高温であつて、前記トロイダル
磁場コイルを極低温にして超電導状態を保持する
には、如何に熱シールド構成を適切に行うかが大
きな課題である。 However, when the toroidal magnetic field coil is made into a superconducting type, this superconducting coil has an extremely low temperature (4.2
〓), and the poloidal magnetic field coil is at room temperature, and the plasma in the plasma container maintained in a high vacuum state is extremely high temperature.In order to maintain the superconducting state by making the toroidal magnetic field coil extremely low temperature, However, a major issue is how to properly configure the heat shield.
一般に超電導装置に用いられる熱輻射シールド
は熱バランスのため熱伝導率の良い銅板やアルミ
板等が採用されている。しかるにトーラス形核融
合装置には前記したようにプラズマを制御したり
安定化させるためのポロイダル磁場コイル群を備
えており、これらのポロイダル磁場コイルにはパ
ルス状通電を行ない、これによつて発生する磁界
をプラズマに作用させる必要がある。従つて従来
一般に採用されている熱伝導率の良いすなわち電
気伝導の良好な銅板やアルミ板を使用する場合に
は、ポロイダル磁場コイルによる磁界が熱輻射シ
ールドにより遮蔽されプラズマに作用しなくな
る。つまり電気伝導の良い熱輻射シールドを用い
た場合には、ポロイダル磁場コイルの磁界によつ
て熱輻射シールドに渦電流が発生しこれによる反
抗磁界によつてプラズマに作用する磁界が弱くな
りポロイダル磁場コイルの磁界が有効に作用しな
い欠点が生じるものと考えられる。 Thermal radiation shields used in superconducting devices generally use copper plates, aluminum plates, etc. with good thermal conductivity for heat balance. However, as mentioned above, the torus-shaped fusion device is equipped with a group of poloidal magnetic field coils for controlling and stabilizing the plasma, and these poloidal magnetic field coils are energized in a pulsed manner, thereby generating It is necessary to apply a magnetic field to the plasma. Therefore, when using a conventionally commonly used copper or aluminum plate with good thermal conductivity, that is, good electrical conductivity, the magnetic field generated by the poloidal magnetic field coil is shielded by the thermal radiation shield and does not act on the plasma. In other words, when a thermal radiation shield with good electrical conductivity is used, the magnetic field of the poloidal magnetic field coil generates eddy currents in the thermal radiation shield, and the resulting countermagnetic field weakens the magnetic field acting on the plasma, weakening the poloidal magnetic field coil. This is thought to result in the drawback that the magnetic field does not work effectively.
本発明はこの点に鑑みてなされたもので、その
目的は、超電導トロイダル磁場コイルを極低温状
態に保持し、かつポロイダル磁場コイルによる発
生磁界をプラズマに有効に作用させて、プラズマ
を安定に制御し得るトーラス形核融合装置を提供
することにある。
The present invention has been made in view of this point, and its purpose is to stably control the plasma by maintaining the superconducting toroidal magnetic field coil at an extremely low temperature and making the magnetic field generated by the poloidal magnetic field coil effectively act on the plasma. The object of the present invention is to provide a torus-shaped nuclear fusion device that can be used.
この目的を達成するため、本発明は、各超電導
トロイダル磁場コイルの口径内に、トーラス大径
の周方向に沿つて分割された複数個の電気的高抵
抗材からなる分割部片と各分割部片間に介挿され
た電気的絶縁物より構成された環状の熱輻射シー
ルドを配置したことを特徴とする。
In order to achieve this object, the present invention provides a plurality of divided sections made of electrically high resistance material divided along the circumferential direction of the large diameter of the torus within the diameter of each superconducting toroidal magnetic field coil, and each divided section. It is characterized by an annular thermal radiation shield made of an electrical insulator inserted between the pieces.
以下、本発明の一実施例を第２図〜第４図につ
いて詳細に説明する。なお、これら図中、第１図
と同一符号は同一物または相当物を示す。
Hereinafter, one embodiment of the present invention will be described in detail with reference to FIGS. 2 to 4. In these figures, the same reference numerals as in FIG. 1 indicate the same or equivalent parts.
この実施例が第１図の従来例と異なる点は、ト
ロイダル磁場コイルとして、従来の常電導コイル
の代りに、液体ヘリウムにより極低温に冷却され
た超電導コイル１１が用いられ、この超電導トロ
イダル磁場コイル１１を極低温状態に保持するた
めに、超電導トロイダル磁場コイル１１の口径内
に円環状の熱輻射シールド管１２からなる第１の
熱輻射シールドが、また超電導トロイダル磁場コ
イル１１の外方にこれを囲むように内側熱輻射シ
ールド筒１３、外側熱輻射シールド筒１４、上側
熱輻射シールドリング１５、下側熱輻射シールド
リング１６からなる第２の熱輻射シールドがそれ
ぞれ設けられ、さらに装置全体が断熱真空容器１
７により覆われて、真空状態に保持されているこ
とである。なお、各熱輻射シールドには冷却管が
装着されており、これに液体窒素を流通させるこ
とにより冷却される。 This embodiment differs from the conventional example shown in FIG. 1 in that a superconducting coil 11 cooled to an extremely low temperature with liquid helium is used as the toroidal magnetic field coil instead of the conventional normal conducting coil. In order to maintain the superconducting toroidal magnetic field coil 11 at an extremely low temperature, a first thermal radiation shield consisting of an annular thermal radiation shield tube 12 is provided within the diameter of the superconducting toroidal magnetic field coil 11, and a first thermal radiation shield consisting of an annular thermal radiation shield tube 12 is provided outside the superconducting toroidal magnetic field coil 11. A second thermal radiation shield consisting of an inner thermal radiation shield tube 13, an outer thermal radiation shield tube 14, an upper thermal radiation shield ring 15, and a lower thermal radiation shield ring 16 is provided to surround the device, and the entire device is insulated under vacuum. container 1
7 and maintained in a vacuum state. Note that each thermal radiation shield is equipped with a cooling pipe, and is cooled by flowing liquid nitrogen through the cooling pipe.
したがつて、装置外部からの熱侵入は断熱真空
容器１７により大部分が阻止され、かつ外部から
真空容器１７の内壁まで侵入してきた熱や、外部
ポロイダル磁場コイル７および変流器コイル９で
発生する熱による輻射熱は、内側、外側熱輻射シ
ールド筒１３，１４および上側、下側熱輻射シー
ルドリング１５，１６からなる第２の熱輻射シー
ルドにより遮断され、さらに超高温のプラズマ１
を閉じ込めたプラズマ容器２や内部ポロイダル磁
場コイル６からの輻射熱は熱輻射シールド管１２
からなる第１の熱輻射シールドにより遮断される
ため、超電導トロイダル磁場コイル１１は極低温
状態に保持されることになる。 Therefore, most of the heat intrusion from the outside of the device is blocked by the heat insulating vacuum container 17, and the heat that has entered from the outside to the inner wall of the vacuum container 17 and the heat generated in the external poloidal magnetic field coil 7 and current transformer coil 9 are prevented. The radiant heat caused by the heat generated by
Radiant heat from the plasma vessel 2 and the internal poloidal magnetic field coil 6 is transferred to the thermal radiation shield tube 12.
The superconducting toroidal magnetic field coil 11 is kept at an extremely low temperature because it is blocked by the first thermal radiation shield consisting of the following.
また、前記各熱輻射シールドの材料としては、
電気抵抗が高くかつ熱遮蔽が良好な材料、例えば
ステンレス鋼板などを用いるのが望ましい。そし
て、プラズマ１に最も近接して配置された熱輻射
シールド管１２は、第３図および第４図に示すよ
うに、トーラス大径の周方向に複数に分割され、
かつ各分割部片１２ａ間には合成樹脂などの電気
絶縁材からなる断面Ｈ形の間隔片１８が介挿され
ている。 In addition, the materials for each of the thermal radiation shields are as follows:
It is desirable to use a material with high electrical resistance and good heat shielding, such as stainless steel plate. The thermal radiation shield tube 12 disposed closest to the plasma 1 is divided into a plurality of parts in the circumferential direction of the large diameter of the torus, as shown in FIGS. 3 and 4.
Further, a spacer piece 18 having an H-shaped cross section and made of an electrically insulating material such as synthetic resin is inserted between each of the divided pieces 12a.
したがつて、各ポロイダル磁場コイル６，７な
どの磁界によつて各熱輻射シールドに発生する渦
電流は大幅に低減され、ポロイダル磁場コイルに
より発生する磁界をプラズマ１に有効に作用させ
てプラズマを安定に制御することができる。 Therefore, the eddy currents generated in each thermal radiation shield by the magnetic fields of the poloidal magnetic field coils 6, 7, etc. are significantly reduced, and the magnetic field generated by the poloidal magnetic field coils is effectively applied to the plasma 1 to generate plasma. It can be controlled stably.
〔発明の効果〕
以上説明したように、本発明によれば、トロイ
ダル磁場コイルとして超電導コイルを用いるにも
かかわらず、これを極低温状態に保持し、かつポ
ロイダル磁場コイルで発生する磁界をプラズマに
有効に作用させてプラズマを安定に制御すること
ができる。[Effects of the Invention] As explained above, according to the present invention, although a superconducting coil is used as a toroidal magnetic field coil, it is maintained at an extremely low temperature and the magnetic field generated by the poloidal magnetic field coil is applied to plasma. The plasma can be controlled effectively and stably.
第１図は従来のトーラス形核融合装置の縦断面
図、第２図は本発明の一実施例に係るトーラス形
核融合装置の縦断面図、第３図は熱輻射シールド
管の平面図、第４図は第３図のＡ部拡大図であ
る。
２……プラズマ容器、６，７……ポロイダル磁
場コイル、１１……超電導トロイダル磁場コイ
ル、１２〜１６……熱輻射シールド。
FIG. 1 is a longitudinal sectional view of a conventional torus-shaped fusion device, FIG. 2 is a longitudinal sectional view of a torus-shaped fusion device according to an embodiment of the present invention, and FIG. 3 is a plan view of a thermal radiation shield tube. FIG. 4 is an enlarged view of section A in FIG. 3. 2... Plasma vessel, 6, 7... Poloidal magnetic field coil, 11... Superconducting toroidal magnetic field coil, 12-16... Thermal radiation shield.
Claims (1)
ズマ容器と、このプラズマ容器内に発生するプラ
ズマを閉じ込める複数個の超電導トロイダル磁場
コイルと、前記プラズマ容器と前記超電導トロイ
ダル磁場コイルの間に配置されてプラズマを制御
するポロイダル磁場コイルとを備えたものにおい
て、前記各超電導トロイダル磁場コイルの口径内
に、トーラス大径の周方向に沿つて分割された複
数個の電気的高抵抗材からなる分割部片と各分割
部片間に介挿された電気的絶縁物より構成された
環状の熱輻射シールドを配置したことを特徴とす
るトーラス形核融合装置。1. An annular plasma container whose interior is maintained in a high vacuum state, a plurality of superconducting toroidal magnetic field coils that confine plasma generated within the plasma container, and a plurality of superconducting toroidal magnetic field coils arranged between the plasma container and the superconducting toroidal magnetic field coils. and a poloidal magnetic field coil for controlling plasma using a poloidal magnetic field coil, wherein a plurality of divided parts made of electrically high resistance materials are divided along the circumferential direction of the large diameter of the torus within the diameter of each of the superconducting toroidal magnetic field coils. A torus-shaped nuclear fusion device, characterized in that an annular thermal radiation shield made of an electrical insulator is inserted between one piece and each divided piece.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58188302A JPS6080787A (en) | 1983-10-11 | 1983-10-11 | Torus-shaped fusion device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58188302A JPS6080787A (en) | 1983-10-11 | 1983-10-11 | Torus-shaped fusion device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6080787A JPS6080787A (en) | 1985-05-08 |
| JPH0472199B2 true JPH0472199B2 (en) | 1992-11-17 |
Family
ID=16221232
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58188302A Granted JPS6080787A (en) | 1983-10-11 | 1983-10-11 | Torus-shaped fusion device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6080787A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0738033B2 (en) * | 1986-10-13 | 1995-04-26 | 株式会社日立製作所 | Shield plate for nuclear fusion device |
-
1983
- 1983-10-11 JP JP58188302A patent/JPS6080787A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6080787A (en) | 1985-05-08 |
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