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JPH0381692A - Fuel supply device of magnetic field confinment type nuclear fusion device - Google Patents

Fuel supply device of magnetic field confinment type nuclear fusion device

Info

Publication number
JPH0381692A
JPH0381692A JP1216751A JP21675189A JPH0381692A JP H0381692 A JPH0381692 A JP H0381692A JP 1216751 A JP1216751 A JP 1216751A JP 21675189 A JP21675189 A JP 21675189A JP H0381692 A JPH0381692 A JP H0381692A
Authority
JP
Japan
Prior art keywords
plasma
limiter
fuel
magnetic field
fuel supply
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.)
Pending
Application number
JP1216751A
Other languages
Japanese (ja)
Inventor
Eiji Fukumoto
英士 福本
Mitsuji Abe
充志 阿部
Shigemi Kinoshita
茂美 木下
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 JP1216751A priority Critical patent/JPH0381692A/en
Publication of JPH0381692A publication Critical patent/JPH0381692A/en
Pending 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

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  • Plasma Technology (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 [産業上の利用分野] 本発明は、磁場閉じ込め型核融合装置の燃料供給装置に
係わり、さらに詳しくはプラズマの形状を決めるリミッ
タから燃料ガスを供給する型式の燃料供給装置に関する
ものである。
[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a fuel supply system for a magnetic field confinement type nuclear fusion device, and more specifically to a type of fuel supply system that supplies fuel gas from a limiter that determines the shape of plasma. It is related to the device.

[従来の技術] 磁場閉じ込め型核融合装置は、周知のように、超高真空
に排気された真空容器内に燃料を供給し電場あるいは磁
場をかけてプラズマを発生させるようになっている。発
生したプラズマの温度、密度等は燃料の供給方法や供給
量に大きく左右されることも知られている。また発生し
たプラズマを長時間安定して保持するには、プラズマ点
火中の燃料の補給や不純物の排気が必要となる。
[Prior Art] As is well known, a magnetic field confinement type nuclear fusion device supplies fuel to a vacuum container evacuated to an ultra-high vacuum and generates plasma by applying an electric or magnetic field. It is also known that the temperature, density, etc. of the generated plasma are greatly affected by the fuel supply method and supply amount. Furthermore, in order to stably maintain the generated plasma for a long time, it is necessary to replenish fuel and exhaust impurities during plasma ignition.

このように、磁場閉じ込め型核融合装置においては、燃
料の供給は重要なことであり従来大別して2つの燃料供
給方法が知られている。1つの方法は燃料ガスを低温に
冷却固化してペレットにし高速でプラズマ中に入射する
方法である。この方法は高温のプラズマ中心に直接燃料
を補給できるという利点があるが、しかしながら、プラ
ズマが存在しない場合にはこの方法は利用できないし、
また燃料はベレットとして供給されるので連続的な燃料
供給ができない等の問題があるので、この燃料供給方法
は単独では利用できず、つぎに述べる第2番目の燃料供
給方法と併用されている。
As described above, in a magnetic field confinement type fusion device, supplying fuel is important, and conventionally, two fuel supply methods are known. One method is to cool the fuel gas to a low temperature, solidify it, make it into pellets, and inject it into the plasma at high speed. This method has the advantage of being able to supply fuel directly to the hot plasma center; however, this method cannot be used in the absence of plasma;
Furthermore, since the fuel is supplied in the form of pellets, there are problems such as the inability to provide continuous fuel supply, so this fuel supply method cannot be used alone and is used in conjunction with the second fuel supply method described below.

第2番目の方法は、ガスパフ法と呼ばれ、真空容器内に
設けられた燃料放出用の開口部からガス状のまま燃料を
供給するもので、その原理的な例が第5図に示されてい
る。即ち、ドーナツ状の真空容器1の上方には燃料ガス
を供給するためのガス供給口5が、そして側方にはプラ
ズマの形状を決めるリミッタ4が設けられている。燃料
供給口5から燃料ガスを真空容器1内に供給し、プラズ
マを発生させると、リミッタ4に接する磁力線の内側に
プラズマ2が閉じこめられる。そして、このプラズマの
外側にスフレイブオフ層3が形成される。
The second method is called the gas puff method, in which fuel is supplied in a gaseous state from a fuel release opening provided in a vacuum container, and an example of its principle is shown in Figure 5. ing. That is, a gas supply port 5 for supplying fuel gas is provided above the donut-shaped vacuum container 1, and a limiter 4 that determines the shape of plasma is provided on the side. When fuel gas is supplied into the vacuum container 1 from the fuel supply port 5 and plasma is generated, the plasma 2 is confined inside the lines of magnetic force that are in contact with the limiter 4. Then, a soflave-off layer 3 is formed outside this plasma.

スフレイブオフ層3は、プラズマの内部から拡散によっ
て洩れ出てきた燃料粒子や不純物粒子が低温のプラズマ
状態で層状になったものである。
The soflave-off layer 3 is a layer of fuel particles and impurity particles leaked out from inside the plasma by diffusion in a low-temperature plasma state.

一般にプラズマ2の中心部は高温のため殆んど全ての粒
子は完全電離状態となっているが、スフレイブオフ層3
の周辺部では低温のため様々なイオン化状態の粒子が存
在し、また粒子のイオン化や再結合が繰り返される。い
わゆるリサイクリングの現象が盛んにおこっており、プ
ラズマからのエネルギの損失の原因となっている。
Generally, the center of the plasma 2 is at a high temperature, so almost all particles are in a completely ionized state, but the sflave-off layer 3
Because of the low temperature, particles in various ionization states exist in the surrounding area, and particles undergo repeated ionization and recombination. The so-called recycling phenomenon is actively occurring and is a cause of energy loss from the plasma.

第5図に示す燃料供給装置において、プラズマ2あるい
はスフレイブオフ層3が存在する状態で、燃料ガス供給
口5から燃料ガスを注入すると、燃料ガス粒子は、高温
のプラズマ中心に達する前に、低温のスフレイブオフ層
3やプラズマ表面近傍で電離されてまう、従って、上記
従来の方法では、プラズマ中心の密度を高めるためには
、大量の燃料を注入しなければならず、大量の燃料を注
入すると、スフレイブオフ層3近傍で起こる燃料粒子の
電離によってプラズマ周辺部からのエネルギの損失も多
くなり、プラズマ周辺部の温度が下ってプラズマ全体が
消滅してしまうという問題がある。
In the fuel supply device shown in FIG. 5, when fuel gas is injected from the fuel gas supply port 5 in the presence of the plasma 2 or the sflobe-off layer 3, the fuel gas particles are transferred to the low-temperature plasma center before reaching the high-temperature plasma center. Therefore, in the conventional method described above, in order to increase the density of the plasma center, a large amount of fuel must be injected. There is a problem in that the ionization of fuel particles occurring in the vicinity of layer 3 also increases the loss of energy from the plasma periphery, causing the temperature of the plasma periphery to drop and the entire plasma to disappear.

上記のような従来のガスバフ方法の欠点あるいは問題点
の解決策が、例えばジャーナルオブニュークリアマテリ
アルズ第121巻(1984)の第285頁から第29
3ページ(“Journal ofNuclear M
aterialg”121(1984)PP285−2
39)に開示されている。この改良されたガスパフ法の
装置の要部を第6図に図示する0図のように、リミッタ
4は、その先端部がプラズマ2とは逆方向に曲率をもっ
ており、その最先端に燃料ガス供給口5が設けられてい
る。
A solution to the drawbacks or problems of the conventional gas buffing method as described above is described, for example, in Journal of Nuclear Materials, Vol. 121 (1984), pp. 285 to 29.
Page 3 (“Journal of Nuclear M
materialg"121 (1984) PP285-2
39). The essential parts of the device for this improved gas puff method are shown in FIG. 6. As shown in FIG. A mouth 5 is provided.

[発明が解決しようとする課題] 第6図に示されている前記従来装置は、燃料ガス供給口
5が最もプラズマに近い位置にあるため、第5図に示さ
れている従来一般のガスパフ法燃料供給装置に比較する
と、プラズマ中心に到達する燃料粒子数が多くなるとい
う効果は期待できるが、しかしながら、以下に述べる2
つの問題点がある。
[Problems to be Solved by the Invention] The conventional device shown in FIG. 6 has the fuel gas supply port 5 closest to the plasma, so it is difficult to solve the conventional gas puff method shown in FIG. Compared to a fuel supply device, the effect of increasing the number of fuel particles reaching the plasma center can be expected; however, the following two
There are two problems.

第1の問題点は、上記のリミッタ4の先端部がプラズマ
2と逆方向に曲率をもっているので、プラズマ2のみな
らずスフレ、イブオフ層3もリミッタ4の先端部に接触
することである。このことは、燃料ガス供給口5の極く
近傍までプラズマから吐き出された低温の不純物粒子が
存在することを意味しており、燃料粒子がプラズマ中心
へ浸透するのを妨げる。
The first problem is that since the tip of the limiter 4 has a curvature in the opposite direction to the plasma 2, not only the plasma 2 but also the soufflé and eve-off layer 3 come into contact with the tip of the limiter 4. This means that low-temperature impurity particles ejected from the plasma exist close to the fuel gas supply port 5, which prevents the fuel particles from penetrating into the center of the plasma.

第2の問題点は、図示されているようにプラズマ2とリ
ミッタ4の接触点が、燃料ガス供給口5と一致している
ことである。一般にプラズマの温度は上記の接触点で最
も低く、この接触点で粒子の電離と再結合の繰返しであ
るリサイクリング現象が最も活発に起っていることが実
験的にも確められている。一方、前記の接触点ではリミ
ッタ4の温度が一番高くなり、リミッタ材の蒸発、リミ
ッタ中に拡散、吸着されていた粒子の放出が最も盛んで
ある。このように、第6図の装置では、プラズマ温度が
低く、不純物粒子の放出が盛んな場所から燃料粒子を注
入することになるので、リサイクリングの活発化、不純
物粒子との荷電交換等を通してプラズマ周辺部が冷却さ
れる可能性が高い。
The second problem is that the contact point between the plasma 2 and the limiter 4 coincides with the fuel gas supply port 5 as shown in the figure. Generally, the temperature of the plasma is lowest at the contact point, and it has been experimentally confirmed that the recycling phenomenon, which is the repeated ionization and recombination of particles, occurs most actively at this contact point. On the other hand, at the contact point, the temperature of the limiter 4 is the highest, and the evaporation of the limiter material and the release of particles that have been diffused and adsorbed into the limiter are most active. In this way, in the device shown in Figure 6, fuel particles are injected from a place where the plasma temperature is low and impurity particles are actively released, so the plasma is increased through active recycling and charge exchange with impurity particles. There is a high possibility that the surrounding area will be cooled.

したがって、本発明は、磁場閉じ込め型核融合装置にお
いて燃料粒子をプラズマ中心まで浸透或は注入でき、且
つ燃料を供給してもプラズマの周辺部の温度の低下が少
ないガスパフ法の燃料供給装置を提供することを目的と
している。また、更には、保守・点検の容易な燃料供給
装置、更には不純物粒子の排気効゛率も高い燃料供給装
置を提供することを目的とする。
Therefore, the present invention provides a gas puff fuel supply device in a magnetic field confinement type fusion device that allows fuel particles to penetrate or inject to the plasma center and that reduces the temperature drop in the peripheral area of the plasma even when fuel is supplied. It is intended to. A further object of the present invention is to provide a fuel supply device that is easy to maintain and inspect, and that also has a high efficiency in exhausting impurity particles.

[課題を解決するための手段〕 前記目的を達成するために、本発明の磁場閉じ込め型核
融合装置の燃料ガス供給装置は特許請求の範囲の請求項
に記載の特徴を有する。
[Means for Solving the Problem] In order to achieve the above object, a fuel gas supply device for a magnetic field confinement type nuclear fusion device of the present invention has the features described in the claims.

[作   用] 本発明によると、リミッタはプラズマとの間に閉じた空
間を形成し、この空間はプラズマ及び真空容器内空間と
は区別された空間を形成しており、この空間はプラズマ
の大部分の表面とは隔離されているので、該閉じた空間
内に形成されるスクレィプオフ層は他の領域におけるス
クレイプオフ層に比較して常に薄くなる。また燃料ガス
を供給するための開口部が該閉じた空間に臨んでいるの
で、プラズマとリミッタとの接触部から該燃料ガス供給
用の開口部を離すことができる。したがって、本発明に
よると、該燃料ガス供給開口から放出された燃料ガスは
、低温のプラズマとリミッタとの接触部と避け、薄いス
クレイプオフ層のみを通してプラズマ内に到達すること
ができ、且つプラズマの周辺部を冷却することが少ない
[Function] According to the present invention, the limiter forms a closed space between it and the plasma, and this space forms a space that is distinct from the plasma and the space inside the vacuum container, and this space forms a closed space between the limiter and the plasma. Since it is isolated from the surface of the part, the scrape-off layer formed within the closed space is always thinner than the scrape-off layer in other areas. Furthermore, since the opening for supplying fuel gas faces the closed space, the opening for supplying fuel gas can be separated from the contact area between the plasma and the limiter. Therefore, according to the present invention, the fuel gas discharged from the fuel gas supply opening avoids the contact between the low temperature plasma and the limiter, and can reach the plasma only through the thin scrape-off layer, and Less cooling of peripheral areas.

C実 施 例コ 本発明の一実施例を第1図及び第2図により説明する。C implementation example An embodiment of the present invention will be described with reference to FIGS. 1 and 2.

第1図は本実施例の磁場閉じ込め型核融合装置のうちリ
ミッタ及びその周辺のみを示した図で、2はプラズマ、
3はスクレプオフ層、4はリミッタ、5は燃料ガス供給
口、6はプラズマ2とリミッタ4とにより形成される閉
じた空間、7はプラズマ2とリミッタ4との接触部、3
′はスクレイプオフ層3のうち前記閉じた空間6内に形
成されたものである。第2図は第1図に示すリミッタ4
のみを示す斜視図である。
Figure 1 is a diagram showing only the limiter and its surroundings in the magnetic field confinement type fusion device of this embodiment, and 2 is a diagram showing the plasma,
3 is a scrap-off layer, 4 is a limiter, 5 is a fuel gas supply port, 6 is a closed space formed by the plasma 2 and the limiter 4, 7 is a contact portion between the plasma 2 and the limiter 4, 3
' is formed in the closed space 6 of the scrape-off layer 3. Figure 2 shows the limiter 4 shown in Figure 1.
FIG.

本実施例においてリミッタ4の先端部は図示の如くラッ
パ形に拡がっており、その最先端部は、ラッパ形の縁の
至る所でプラズマと接触する接触部7を威すように、そ
の形が加工されている。このような形状のリミッタ4を
プラズマ中に挿入すると、第1図に示す如くプラズマ2
とリミッタ4との間にプラズマ2及び真空容器内空間と
は区別される閉じた空間6が形成される。プラズマ2の
外側に形成されるスクレイプオフ層3は、プラズマ中か
ら拡散によってプラズマ表面を横切って外へ出てきた粒
子から成る。したがってスクレイプオフ層3の厚さは、
それとつながるプラズマ表面積の大小によって決まり、
プラズマ表面積が小さい程薄い。前記閉じた空間6内で
は、それと対向するプラズマ表面積が全プラズマ表面積
に比べて非常に小さいので、該空間6内のスクレイプオ
フ層3′の厚さは他の部分のスクレイプオフ層3に比べ
て薄くなる。
In this embodiment, the tip of the limiter 4 is expanded into a trumpet shape as shown in the figure, and the tip of the limiter 4 is shaped so as to threaten the contact portion 7 that comes into contact with the plasma throughout the edge of the trumpet shape. Processed. When the limiter 4 having such a shape is inserted into the plasma, the plasma 2 is changed as shown in FIG.
A closed space 6 is formed between the plasma 2 and the limiter 4, which is distinguished from the plasma 2 and the space inside the vacuum container. The scrape-off layer 3 formed outside the plasma 2 is composed of particles that have come out from the plasma by diffusion across the plasma surface. Therefore, the thickness of the scrape-off layer 3 is
It is determined by the size of the plasma surface area connected to it.
The smaller the plasma surface area, the thinner it is. In the closed space 6, the plasma surface area facing the closed space 6 is very small compared to the total plasma surface area, so the thickness of the scrape-off layer 3' in the space 6 is smaller than that of the scrape-off layer 3 in other parts. Become thin.

また本実施例における燃料ガス供給口5は、プラズマ2
とリミッタ4との接触部7から最も離れて閉じた空間6
内に向けてリミッタ4に設けられている。このため、該
燃料ガス供給口5は、プラズマ温度が低くて不純物放出
量の多い前記接触部7からは離れている構造となってい
る。
Further, in this embodiment, the fuel gas supply port 5 is connected to the plasma 2
and the closed space 6 farthest from the contact part 7 with the limiter 4
The limiter 4 is provided facing inward. For this reason, the fuel gas supply port 5 is located away from the contact portion 7 where the plasma temperature is low and the amount of impurity released is large.

以上のように構成された本実施例によれば、燃料ガス供
給口5から放出された燃料粒子は薄いスクレイプオフ、
1513’ のみを通ってプラズマ表面に到達できるた
め、従来技術に比べて燃料粒子のプラズマ中への到達率
が高い。
According to this embodiment configured as described above, the fuel particles discharged from the fuel gas supply port 5 are thin scraped off particles,
Since the fuel particles can reach the plasma surface only through 1513', the rate of fuel particles reaching the plasma is higher than in the prior art.

第3図は本発明の他の実施例である磁場閉じ込め型核融
合装置のリミッタ近傍の斜視図である。
FIG. 3 is a perspective view of the vicinity of the limiter of a magnetic field confinement type fusion device which is another embodiment of the present invention.

この図において1は真空容器であり、リミッタ4及び燃
料ガス供給口5はそれぞれ別々に前記真空容器1に設け
られている。燃料ガス供給口5はリミツタ4内部の空間
6の底部に開口している。リミッタ4は略箱形であるが
、その先端はプラズマとの接触部7を成すように形状加
工されている。
In this figure, 1 is a vacuum vessel, and a limiter 4 and a fuel gas supply port 5 are each separately provided in the vacuum vessel 1. The fuel gas supply port 5 opens at the bottom of the space 6 inside the limiter 4. The limiter 4 is approximately box-shaped, but its tip is shaped to form a contact portion 7 with the plasma.

本実施例においてもプラズマとリミッタ4との接触部7
によって閉じた空M6が形成されるから前記第1の実施
例と同様の効果を得ることができる。
Also in this embodiment, the contact portion 7 between the plasma and the limiter 4
Since a closed air M6 is formed by this, the same effect as in the first embodiment can be obtained.

さらに本実施例では、これに加えて、リミッタ4と燃料
ガス供給口5が別々になっているので、リミッタ4の交
換や保守が簡単になるという効果がある。
Furthermore, in this embodiment, in addition to this, since the limiter 4 and the fuel gas supply port 5 are separate, there is an effect that the limiter 4 can be easily replaced and maintained.

本発明の更に他の実施例である磁場閉じ込め型核融合装
置のポロイダル断面図を第4図に示す。
FIG. 4 shows a poloidal cross-sectional view of a magnetic field confinement type fusion device which is still another embodiment of the present invention.

この図において、他の図と同等の部品は同じ番号を付し
て示す、8は排気ポンプ、9は燃料粒子の入射の方向を
示す矢印、10は不純物粒子の流れの方向を示す矢印で
ある。本実施例は、リミッタ4及び燃料供給口5の構造
は、第1図、第2図に示されている実施例のものと同じ
であるが、リミッタ4を冷却装置11を内蔵している箱
体12に取り付け、この箱体内に排気ポンプ8を設けて
いる点で相違している0箱体12は、真空容器1に連結
された壁13に取り付けられている。排気ポンプ8を動
作させることによりプラズマ2から拡散により排出され
た粒子はスクレイプオフ層3を通ってリミタ−4の背後
に導びかれ、箱体12の端壁の透孔14を通して排気さ
れる。したがって本実施例によれば第I実施例と同様に
燃料供給効率が高まるばかりでなく、不純物粒子等の排
気効率も高めることができる。
In this figure, parts that are equivalent to those in other figures are given the same numbers. 8 is an exhaust pump, 9 is an arrow indicating the direction of incidence of fuel particles, and 10 is an arrow indicating the direction of flow of impurity particles. . In this embodiment, the structure of the limiter 4 and the fuel supply port 5 is the same as that of the embodiment shown in FIGS. The box body 12 is attached to a wall 13 connected to the vacuum vessel 1, and is different in that an exhaust pump 8 is provided inside the box body. By operating the exhaust pump 8, the particles diffused out of the plasma 2 are led behind the limiter 4 through the scrape-off layer 3, and are exhausted through the through hole 14 in the end wall of the box 12. Therefore, according to this embodiment, not only the fuel supply efficiency can be improved as in the first embodiment, but also the efficiency of exhausting impurity particles and the like can be improved.

[発明の効果] 以上のように、本発明によると、リミッタはプラズマと
の間に、プラズマ及び真空容器内空間とは区別できる閉
じた空間を形成しており、この閉じた空間内に燃料ガス
供給用の開口部が臨んでいるので、燃料ガス供給用の開
口部前面のスクレイプオフ層は他の領域のスクレイプオ
フ層より薄くなり、またプラズマとリミッタとの接触位
置が燃料ガス供給用の開口部とは離れているので、プラ
ズマに対する燃料供給効率が高められると共に、プラズ
マ周辺部が冷却されることが少ないという効果が得られ
る。
[Effects of the Invention] As described above, according to the present invention, the limiter forms a closed space between itself and the plasma that can be distinguished from the plasma and the space inside the vacuum container, and the fuel gas is injected into this closed space. Since the supply opening is facing, the scrape-off layer in front of the fuel gas supply opening is thinner than the scrape-off layer in other areas, and the point of contact between the plasma and the limiter is close to the fuel gas supply opening. Since the plasma is separated from the surrounding area, the efficiency of fuel supply to the plasma is increased and the peripheral area of the plasma is less likely to be cooled.

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

第1図は本発明の1実施例の要部のみを示す断面図、第
2図は第1図に示すリミッタの斜視図、第3図は本発明
の他の実施例の要部を示す斜視図、第4図は更に他の実
施例の要部断面図、第5図、第6図はそれぞれ異なる従
来例を示す断面図である。 l・・・真空容器   2・・・プラズマ3.3′・・
・スクレイプオフ層 4・・・リミッタ   5・・・燃料ガス供給用開口部
6・・・閉じた空間  8・・・排気ポンプ(他1名) 第 図 2アフスマ 6 第 図 第 図 第 第 図 燃料ガス く
FIG. 1 is a sectional view showing only the main parts of one embodiment of the present invention, FIG. 2 is a perspective view of the limiter shown in FIG. 1, and FIG. 3 is a perspective view showing the main parts of another embodiment of the invention. 4 are sectional views of essential parts of still another embodiment, and FIGS. 5 and 6 are sectional views showing different conventional examples. l...Vacuum container 2...Plasma 3.3'...
・Scrape-off layer 4...Limiter 5...Fuel gas supply opening 6...Closed space 8...Exhaust pump (1 other person) Fig. 2 Afsuma 6 Fig. Fig. Fig. Fig. Fig. Fuel gas

Claims (1)

【特許請求の範囲】 1 真空容器内にてプラズマに接触してその形を決める
ためのリミッタから前記プラズマに燃料ガスを供給する
ようにした磁場閉じ込め型核融合装置の燃料供給装置に
おいて、前記リミッタはプラズマとの間に閉じた空間を
形成する形状に構成されていると共に、該閉じた空間内
に燃料ガスを注入するための開口部が臨んでいることを
特徴とする磁場封じ込め型核融合装置の燃料供給装置。 2 前記リミッタは燃料ガス注入用の前記開口部とは独
立して真空容器から取り外し自在である請求項1記載の
磁場封じ込め型核融合装置の燃料供給装置。 3 前記リミッタの前記プラズマから遠い側には排気ポ
ンプが設けられている請求項1又は2記載の磁場封じ込
め型核融合装置の燃料供給装置。
[Scope of Claims] 1. A fuel supply device for a magnetic field confinement type nuclear fusion device in which fuel gas is supplied to the plasma from a limiter for contacting the plasma and determining its shape in a vacuum vessel, wherein the limiter A magnetic field confinement type nuclear fusion device characterized in that it is configured in a shape that forms a closed space between it and the plasma, and that an opening for injecting fuel gas faces into the closed space. fuel supply system. 2. The fuel supply system for a magnetic field confinement type fusion device according to claim 1, wherein the limiter is removable from the vacuum vessel independently of the opening for fuel gas injection. 3. The fuel supply system for a magnetic field confinement type fusion device according to claim 1 or 2, wherein an exhaust pump is provided on a side of the limiter far from the plasma.
JP1216751A 1989-08-23 1989-08-23 Fuel supply device of magnetic field confinment type nuclear fusion device Pending JPH0381692A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1216751A JPH0381692A (en) 1989-08-23 1989-08-23 Fuel supply device of magnetic field confinment type nuclear fusion device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1216751A JPH0381692A (en) 1989-08-23 1989-08-23 Fuel supply device of magnetic field confinment type nuclear fusion device

Publications (1)

Publication Number Publication Date
JPH0381692A true JPH0381692A (en) 1991-04-08

Family

ID=16693354

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1216751A Pending JPH0381692A (en) 1989-08-23 1989-08-23 Fuel supply device of magnetic field confinment type nuclear fusion device

Country Status (1)

Country Link
JP (1) JPH0381692A (en)

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