JPS648315B2 - - Google Patents
Info
- Publication number
- JPS648315B2 JPS648315B2 JP55153864A JP15386480A JPS648315B2 JP S648315 B2 JPS648315 B2 JP S648315B2 JP 55153864 A JP55153864 A JP 55153864A JP 15386480 A JP15386480 A JP 15386480A JP S648315 B2 JPS648315 B2 JP S648315B2
- Authority
- JP
- Japan
- Prior art keywords
- diverter
- header
- fusion device
- cooling pipe
- inlet
- 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
Links
- 238000001816 cooling Methods 0.000 claims description 22
- 230000004927 fusion Effects 0.000 claims description 14
- 239000002826 coolant Substances 0.000 claims description 8
- 238000010586 diagram Methods 0.000 description 4
- 239000002245 particle Substances 0.000 description 2
- 230000004907 flux Effects 0.000 description 1
- 238000006386 neutralization reaction Methods 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】
本発明は核融合装置のダイバータに係り、特に
核融合装置の粒子中性化のために排気ダクトの近
傍に設置される核融合装置のダイバータに関する
ものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a diverter for a nuclear fusion device, and more particularly to a diverter for a nuclear fusion device installed near an exhaust duct for particle neutralization of the nuclear fusion device.
従来から、核融合装置やイオン加速器等では電
離した粒子を中性化するためにダイバータが用い
られている。このダイバータは冷却材を通流した
冷却管を配したプレートを磁力線に対してこれを
さえ切る様に配置される。 2. Description of the Related Art Diverters have conventionally been used in nuclear fusion devices, ion accelerators, and the like to neutralize ionized particles. This diverter is arranged so that a plate with a cooling pipe through which a coolant flows is cut across the magnetic field lines.
第1図に従来のダイバータを用いた核融合装置
の部分断面図を示す。該図において1はプラズ
マ、2はプラズマ閉じ込め用のブランケツト、3
は遮蔽体、4はドロイダルコイル、5はポロイダ
ルコイル、6はダイバータである。 FIG. 1 shows a partial cross-sectional view of a nuclear fusion device using a conventional divertor. In the figure, 1 is a plasma, 2 is a blanket for plasma confinement, and 3 is a plasma confinement blanket.
is a shield, 4 is a droidal coil, 5 is a poloidal coil, and 6 is a diverter.
従来例のダイバータ6の詳細図を第2図に示
す。ダイバータ6は、冷却材の入口、出口用のヘ
ゾダー7、両ヘツダーに両端を接続され冷却材が
流れる冷却管を複数個配置した冷却管群8、該冷
却管群によつて冷却されるプレート(図示省略)
から構成される。該図において、プラズマ1が極
短時間で消滅した場合に発生する渦電流の方向を
矢印9で示す。この時に発生する電磁力の方向を
矢印10で示す。この時、冷却管群8と入口、出
口ヘツダー7に形成される渦電流のループ(以下
単にループと言う)は第3図のようになる。 A detailed diagram of a conventional diverter 6 is shown in FIG. The diverter 6 includes a header 7 for the inlet and outlet of the coolant, a cooling tube group 8 in which a plurality of cooling tubes are connected at both ends to both headers and through which the coolant flows, and a plate cooled by the cooling tube group ( (Illustrations omitted)
It consists of In the figure, an arrow 9 indicates the direction of an eddy current generated when the plasma 1 disappears in a very short time. The direction of the electromagnetic force generated at this time is indicated by an arrow 10. At this time, an eddy current loop (hereinafter simply referred to as a loop) formed in the cooling tube group 8 and the inlet and outlet headers 7 becomes as shown in FIG.
第3図に示すように、従来の核融合装置のダイ
バータ6では、入口と出口用のヘツダー7が離れ
て配置されているため、ダイバータ6を構成して
いる冷却管群8と入口、出口ヘツダー7がつくる
ループは大きな面積を形成している。このため、
プラズマ1が極短時間(〜10ms程度)で消滅し
た場合に大きな渦電流が発生し、この渦電流とト
ロイダルコイル4が作る磁場とによつて大きな電
磁力(〜5t/m程度)が生じ、この電磁力によつ
てダイバータ6は破損する恐れがあつた。即ち、
プラズマ1が消滅した場合に発生する電磁力は、
プラズマ電流が変化することによつて生じる渦電
流j→とトロイダコイル4のつくる磁場B→tとのベ
クトル積j→×B→tによつて発生する。ダイバータ
6に発生する渦電流jは、ダイバータ6を構する
冷却管群8と出入口ヘツダー7とによつてつくら
れるループが形成する面Sを通過する面Sに垂直
な磁束密度Boの時間変化によつて与えられる。
つまり、次式で表わされる。 As shown in FIG. 3, in the diverter 6 of the conventional fusion device, the inlet and outlet headers 7 are arranged separately, so the cooling tube group 8 making up the diverter 6 and the inlet and outlet headers are separated. The loop created by 7 forms a large area. For this reason,
When the plasma 1 disappears in an extremely short time (about 10ms), a large eddy current is generated, and this eddy current and the magnetic field created by the toroidal coil 4 generate a large electromagnetic force (about 5t/m). There was a risk that the diverter 6 would be damaged by this electromagnetic force. That is,
The electromagnetic force generated when plasma 1 disappears is
It is generated by the vector product j→×B→ t of the eddy current j→ caused by a change in the plasma current and the magnetic field B→t created by the toroidal coil 4. The eddy current j generated in the diverter 6 is caused by a time change in the magnetic flux density B o perpendicular to the surface S that passes through the surface S formed by the loop formed by the cooling tube group 8 and the entrance/exit header 7 that make up the diverter 6. given by.
That is, it is expressed by the following formula.
j=−1/R d/dt∫sBods (Rはループの電気抵抗)。 j=-1/R d/dt∫ s B o ds (R is the electrical resistance of the loop).
しかし、上述した如く、従来の核融合装置のダ
イバータ6は出入口ヘツダー7が離れて配置され
ているため、冷却管群8とヘツダー7とによつて
大きな面積を有するループが形成されていた。こ
のため、上述した式で与えられる渦電流jは大き
な値となり、電磁力によりダイバータ6が破損に
至つてしまうのである。 However, as described above, in the diverter 6 of the conventional fusion device, the inlet/outlet header 7 is arranged at a distance, so the cooling tube group 8 and the header 7 form a loop having a large area. For this reason, the eddy current j given by the above-mentioned formula becomes a large value, and the diverter 6 ends up being damaged by the electromagnetic force.
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、冷却管群とヘツダーによつ
て構成されるものであつても、渦電流の大きさを
ほぼ零に近い値にし、電磁力により破損すること
のない様にした核融合装置のダイバータを提供す
るにある。 The present invention has been made in view of the above points, and its purpose is to reduce the magnitude of eddy current to a value close to zero even in a device composed of a group of cooling tubes and a header. An object of the present invention is to provide a diverter for a nuclear fusion device that is not damaged by electromagnetic force.
本発明はプラズマ閉じ込め用ブランケツトの排
気ダクトの入口側近傍に設けられたダイバータに
おいて、冷却材を通流させる冷却管群へ冷却材を
出し入れする出口ヘツダーと入口ヘツダーとを隣
接して配置すると共に、前記冷却管群のそれぞれ
の冷却管を折り返し形状として前記隣接して配置
された入口ヘツダーおよび出口ヘツダーに接続す
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 provides a diverter provided near the inlet side of an exhaust duct of a plasma confinement blanket, in which an outlet header and an inlet header are arranged adjacent to each other for introducing and removing coolant into a group of cooling pipes through which coolant flows. The desired purpose is achieved by forming each cooling pipe of the cooling pipe group into a folded shape and connecting it to the adjacently arranged inlet header and outlet header.
以下図面の実施例に基づいて本発明を説明す
る。尚、従来と同一のものは同符号を用いて説明
する。 The present invention will be described below based on embodiments shown in the drawings. Components that are the same as those in the prior art will be explained using the same reference numerals.
第4図、第5図、及び第6図に本発明の一実施
例であるダイバータ6(プレートは図示せず)を
示す。他の構造は従来のものとほとんど同様のた
め、ここでの説明は省略する。 FIG. 4, FIG. 5, and FIG. 6 show a diverter 6 (plate not shown) which is an embodiment of the present invention. The other structures are almost the same as those of the conventional structure, so the explanation here will be omitted.
該図に示す本実施例では、入口、及び出口側ヘ
ツダー7をほぼ同様な位置に隣接させて配置し、
2本ずつ1対とした冷却管群8(両端の2対のみ
図示)によつてダイバータ6を形成している。 In this embodiment shown in the figure, the inlet and outlet side headers 7 are arranged adjacently at substantially the same position,
A diverter 6 is formed by a cooling tube group 8 made up of two pairs (only two pairs at both ends are shown).
このような本実施例のダイバータ6の構成によ
れば、冷却管群8と出入口ヘツダー7によつてつ
くられるループは第7図に示すようになり、従来
のダイバータ6がつくるループ第3図と、本実施
例のダイバータ6がつくるループ第7図を比較す
れば本実施例でのループが形成する面の面積は、
第3図に比べて零に近いので、プラズマ電流が極
短時間で消滅しても、大きな渦電流を発生しな
い。従つて、大きな電磁力を発生することはな
く、ダイバータ6が破損に至るようなことはな
い。 According to the configuration of the diverter 6 of this embodiment, the loop created by the cooling tube group 8 and the inlet/outlet header 7 is as shown in FIG. 7, which is different from the loop created by the conventional diverter 6 in FIG. , Comparing the loop formed by the diverter 6 of this embodiment in FIG. 7, the area of the surface formed by the loop in this embodiment is
Since it is closer to zero than in FIG. 3, even if the plasma current disappears in an extremely short time, no large eddy current is generated. Therefore, no large electromagnetic force is generated, and the diverter 6 will not be damaged.
以上説明した本発明の核融合装置のダイバータ
によれば、冷却管群へ冷却材を出し入れする出口
ヘツダーと入口ヘツダーとを隣接させて設置した
ものであるから、冷却管群と出入口ヘツダーとで
形成されるループを小さくすることができるので
大きな電磁力が発生しないため、ダイバータの破
損を防ぐことができる。 According to the diverter of the nuclear fusion device of the present invention described above, the outlet header and the inlet header, which take coolant in and out of the cooling tube group, are installed adjacent to each other. Since the loop that is generated can be made small, large electromagnetic force is not generated, and damage to the diverter can be prevented.
第1図は核融合装置を示す部分断面図、第2図
は従来の核融合装置のダイバータを示す斜視図、
第3図は従来のダイバータにおいて形成されるル
ープを示す図、第4図は本発明の核融合装置のダ
イバータの一実施例を示す斜視図、第5図はその
側面図、第6図はその正面図、第7図は本発明の
一実施例のダイバータにおいて形成されるループ
を示す図である。
1…プラズマ、2…ブランケツト、3…遮蔽
体、4…トレイダルコイル、5…ポロイダルコイ
ル、6…ダイバータプレート、7…ヘツダー、8
…冷却管群、9…渦電流の方向、10…電磁力の
方向。
FIG. 1 is a partial sectional view showing a fusion device, FIG. 2 is a perspective view showing a diverter of a conventional fusion device,
FIG. 3 is a diagram showing a loop formed in a conventional diverter, FIG. 4 is a perspective view showing an embodiment of the diverter of the fusion device of the present invention, FIG. 5 is a side view thereof, and FIG. 6 is a diagram thereof. The front view, FIG. 7, is a diagram showing a loop formed in a diverter according to an embodiment of the present invention. 1... Plasma, 2... Blanket, 3... Shielding body, 4... Traidal coil, 5... Poloidal coil, 6... Diverter plate, 7... Header, 8
... Cooling pipe group, 9 ... Direction of eddy current, 10 ... Direction of electromagnetic force.
Claims (1)
ツダーと、該両ヘツダーに両端を接続され冷却材
が流れる冷却管を複数個配置した冷却管群と、該
冷却管群によつて冷却されるプレートとを有する
核融合装置のダイバータにおいて、 前記出口ヘツダーおよび入口ヘツダーを隣接し
て配置すると共に、前記冷却管群のそれぞれの冷
却管を折り返し形状として前記隣接して配置され
た出口ヘツダーおよび入口ヘツダーに接続したこ
とを特徴とする核融合装置のダイバータ。[Scope of Claims] 1. A cooling pipe group including an outlet header and an inlet header for taking in and out coolant, a plurality of cooling pipes connected at both ends to the headers and through which the coolant flows, and a cooling pipe group formed by the cooling pipe group. In the diverter for a nuclear fusion device, the outlet header and the inlet header are arranged adjacent to each other, and each cooling pipe of the cooling pipe group is formed into a folded shape so that the adjacently arranged outlet A diverter for a nuclear fusion device, characterized in that it is connected to a header and an inlet header.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55153864A JPS5777992A (en) | 1980-11-04 | 1980-11-04 | Divertor for nuclear fusion device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP55153864A JPS5777992A (en) | 1980-11-04 | 1980-11-04 | Divertor for nuclear fusion device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5777992A JPS5777992A (en) | 1982-05-15 |
| JPS648315B2 true JPS648315B2 (en) | 1989-02-13 |
Family
ID=15571764
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP55153864A Granted JPS5777992A (en) | 1980-11-04 | 1980-11-04 | Divertor for nuclear fusion device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5777992A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS608781A (en) * | 1983-06-29 | 1985-01-17 | 株式会社日立製作所 | Cooling device for magnetic limiter of nuclear fusion device |
| JPS6040989A (en) * | 1983-08-15 | 1985-03-04 | 日本原子力研究所 | Magnetic limiter cooling device for fusion device |
| JP2821583B2 (en) * | 1991-04-12 | 1998-11-05 | 株式会社日立製作所 | Vacuum container for neutral particle injection device and fusion device |
-
1980
- 1980-11-04 JP JP55153864A patent/JPS5777992A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5777992A (en) | 1982-05-15 |
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