JPH01105190A - Fusion reactor wall - Google Patents
Fusion reactor wallInfo
- Publication number
- JPH01105190A JPH01105190A JP62261579A JP26157987A JPH01105190A JP H01105190 A JPH01105190 A JP H01105190A JP 62261579 A JP62261579 A JP 62261579A JP 26157987 A JP26157987 A JP 26157987A JP H01105190 A JPH01105190 A JP H01105190A
- Authority
- JP
- Japan
- Prior art keywords
- protective
- reactor wall
- fusion reactor
- wall
- tile
- 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.)
- Granted
Links
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
- Manufacture And Refinement Of Metals (AREA)
- 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〕
本発明は核融合炉の炉心プラズマを包む第一壁(以下炉
壁と呼ぶ)に係り、特に、炉壁の炉心プラズマ側を構成
する防護タイルの脱ガスを効果的に行うのに好適な核融
合炉壁の構造に関する。[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a first wall (hereinafter referred to as the reactor wall) that encloses the core plasma of a nuclear fusion reactor, and particularly relates to a protection device that constitutes the core plasma side of the reactor wall. The present invention relates to a structure of a fusion reactor wall suitable for effectively degassing tiles.
従来、核融合炉壁については、特開昭58−24633
号公報、ある′いは、実顆昭60−142877号明細
書に記載のように、プラズマに面する防護タイルは絶縁
体、または、半導体材料であって、これが金属基板に接
合されるか、または、黒鉛などの導電性材料が絶縁層を
介して金属基板に接合または機械的に締結された構造と
なっており、これらの防護タイルは金属基板と電気的に
導通状態であるか、または、隣接する防護タイル間は電
気的に絶縁状態におかれていた。Conventionally, regarding fusion reactor walls, Japanese Patent Application Laid-Open No. 58-24633
As described in Japanese Pat. Alternatively, it has a structure in which a conductive material such as graphite is bonded or mechanically fastened to a metal substrate via an insulating layer, and these protective tiles are electrically connected to the metal substrate, or Adjacent protective tiles were electrically insulated.
上記従来技術による核融合炉壁では、防護タイルの真空
脱ガスを行う場合、真空容器の加熱により輻射を利用し
て間接的に炉壁を加熱する方法、冷却基板内に設けられ
た冷却チャンネル内に加熱媒体1例えば、高温のガスを
循環させる方法、または、炉心部にプラズマを形成して
から閉じ込め磁場を変化させプラズマのエネルギを炉壁
面に与えて炉壁を加熱する方法などがとられていた。し
かし間接的加熱法では大きな熱容量をもつ真空容器全体
を加熱する必要があり、加熱に長時間、かつ、大電力を
必要とする欠点があった。冷却チャンネル内に高温ガス
を循環させる方法は効果的ではあるが冷却基板に苛酷な
温度サイクルを与えることになり、また、到達温度も限
られている。プラズマ自体による加熱法は加熱時間が数
十msと短かく、プラズマエネルギの入射領域を自由に
制御することは困難であった。In the case of the fusion reactor wall according to the above conventional technology, when performing vacuum degassing of the protective tiles, there is a method of indirectly heating the reactor wall using radiation by heating the vacuum container, For example, methods are used to circulate high-temperature gas, or to form plasma in the reactor core and then change the confining magnetic field to apply plasma energy to the reactor wall to heat the reactor wall. Ta. However, the indirect heating method has the disadvantage that it is necessary to heat the entire vacuum container, which has a large heat capacity, and that heating takes a long time and requires a large amount of electric power. Although effective, circulating hot gas within the cooling channels subjects the cooled substrate to severe temperature cycling and is limited in the temperatures that can be reached. In the heating method using plasma itself, the heating time is as short as several tens of milliseconds, and it is difficult to freely control the incident region of plasma energy.
本発明の特徴は、こうした炉壁を効率よく加熱して、脱
ガスを行うことにある。A feature of the present invention is that the furnace walls are efficiently heated to degas.
上記目的は、冷却基板と電気的に絶縁され、−方、相互
に電気的に接続された複数個の防護タイルに直接通電・
加熱を行うことにより達成される。The above purpose is to directly energize multiple protective tiles that are electrically insulated from the cooling board and electrically connected to each other.
This is achieved by heating.
第2図は磁場閉じ込め型核融合炉の断面構造を示す模式
図である。本発明の炉壁1は真空容器2とプラズマ3の
間に設置され、真空容器2をプラズマ3から流入する熱
負荷、及び、 負荷から防護するためのものである。FIG. 2 is a schematic diagram showing the cross-sectional structure of a magnetic field confinement type fusion reactor. The furnace wall 1 of the present invention is installed between the vacuum vessel 2 and the plasma 3 to protect the vacuum vessel 2 from the heat load and load flowing from the plasma 3.
プラズマ3はトロイダルコイル4.ポロイダルコイル5
およびプラズマ電流により誘起される平衡磁場によりト
ーラス状に形成される。従って、炉壁1はトーラスの内
側の真空壁と外側の真空壁を防護する二部分に分割され
るのが一般的である。炉壁のプラズマに面する側は防護
タイル6で覆われており、一方、真空容器2の側には防
護タイル6との間の熱接触を図るための中間材7を介し
て冷却基板8が置かれ、プラズマから防護壁面に流入す
る熱の除去が行われる。炉壁面上の防護タイルは、順次
、電気的に接続され、炉壁の端面に設けられた電流端子
9に接続されて抵抗回路を形成する。このような防護タ
イルよりなる回路に接続されたリード線10に電力を供
給することにより、防護壁の加熱を行い、防護壁表面の
効率良い脱ガスが行える。Plasma 3 is a toroidal coil 4. Poloidal coil 5
and is formed into a torus shape by the balanced magnetic field induced by the plasma current. Therefore, the furnace wall 1 is generally divided into two parts, protecting the inner vacuum wall and the outer vacuum wall of the torus. The side of the furnace wall facing the plasma is covered with a protective tile 6, while a cooling substrate 8 is placed on the side of the vacuum vessel 2 via an intermediate material 7 for thermal contact with the protective tile 6. heat flowing from the plasma into the protective wall surface is removed. The protective tiles on the furnace wall are sequentially electrically connected and connected to current terminals 9 provided on the end face of the furnace wall to form a resistance circuit. By supplying power to the lead wire 10 connected to the circuit made of such a protective tile, the protective wall can be heated and the surface of the protective wall can be efficiently degassed.
以下、本発明の一実施例を第1図により説明する。防護
タイル6は冷却チャネル11をもつ冷却基板8上に熱伝
導性の良好な中間材7を介して冶金的、あるいは、機械
的方法により締結される。An embodiment of the present invention will be described below with reference to FIG. The protective tile 6 is fastened onto a cooling substrate 8 having cooling channels 11 via an intermediate material 7 with good thermal conductivity by metallurgical or mechanical methods.
中間材は、応力緩和性に優れた炭素繊維強化銅(または
アルミニウム)材、モリブデン、バナジウム、あるいは
、チタンおよびそれらを基体とする合金、銅、タングス
テン、または、黒鉛製の繊維で造られたフェルト、また
は、繊布が適している。防護タイル6は黒鉛、TiC,
SiCおよびそれらの複合材、あるいは、金属ベリリウ
ムよりなる防護材13と冷却基板8側に置かれた電気的
絶縁1fH4で構成される。電気的絶縁層は熱伝導性に
優れたダイヤモンド、SiCまたはBN。The intermediate material is carbon fiber-reinforced copper (or aluminum) material with excellent stress relaxation properties, felt made of molybdenum, vanadium, titanium and alloys based on them, copper, tungsten, or graphite fibers. , or textiles are suitable. The protective tile 6 is made of graphite, TiC,
It is composed of a protective material 13 made of SiC, a composite material thereof, or metal beryllium, and an electrical insulator 1fH4 placed on the cooling board 8 side. The electrical insulating layer is made of diamond, SiC, or BN, which has excellent thermal conductivity.
AQN、5iaN+などが適しており、特に、気相合成
法で形成されたダイヤモンド膜、1〜2重量%のBeO
を含有するSiC焼結体が望ましい。AQN, 5iaN+, etc. are suitable, especially diamond films formed by vapor phase synthesis, 1-2% by weight BeO
A SiC sintered body containing is desirable.
SiC,BN、AQNなどの絶縁層の形成は、原料粉を
防護材13として使用する黒鉛、または、セラミックス
材上に直接、加圧(または常圧)焼結法により形成する
ことにより、接合界面における熱接触抵抗値の小さい積
層型防護タイル6を実現することができる。防護タイル
6の側面の底面と成す角度は30’〜80°とし、防護
タイルの基底部の断面が台形となるように加工しである
。The insulating layer of SiC, BN, AQN, etc. is formed by directly forming the raw material powder on the graphite or ceramic material used as the protective material 13 by pressurized (or normal pressure) sintering, so that the bonding interface is It is possible to realize a laminated protective tile 6 with a small thermal contact resistance value. The angle formed by the side surface of the protective tile 6 with the bottom surface is 30' to 80°, and the cross section of the base of the protective tile is processed to be trapezoidal.
隣接する防護壁タイル間の間隙には、楔形断面をもつ楔
形接続子12を、防護タイルの側面と密着するように挿
入し、隣接防護タイル間の電気的接触を図る。楔形接続
子のプラズマに面する側は黒鉛などの電気的良導体で、
一方、冷却基板側は絶縁層14で形成した二層構造とす
ることにより、防護材13と冷却基板8との絶縁を図っ
ている。A wedge-shaped connector 12 having a wedge-shaped cross section is inserted into the gap between adjacent protective wall tiles so as to be in close contact with the side surface of the protective tile, thereby establishing electrical contact between the adjacent protective tiles. The side of the wedge-shaped connector facing the plasma is made of a good electrical conductor such as graphite.
On the other hand, the cooling board side has a two-layer structure formed of an insulating layer 14 to insulate the protective material 13 and the cooling board 8.
相互に結合された防護タイル6の列の終端部に位置する
防護タイル6の側面には接続端子9が接続され、防護タ
イルの通電加熱用端子として使用される。防護タイルは
通電加熱により、特に、板面方向に膨張し、防護壁間の
間隔は温度上昇と共に減少する。楔形接続子12と防護
タイル6の接触面を、例えば、黒鉛のような摩擦係数の
小さい材料で構成しておくことにより、防護タイル12
の熱膨張と共に楔形接続子12が第2図の上方、すなわ
ち、プラズマ側に押し上げられることにより、防護タイ
ル6の熱膨張を吸収することが出来る。A connecting terminal 9 is connected to the side surface of the protective tile 6 located at the end of the row of mutually coupled protective tiles 6, and is used as a terminal for energizing the protective tile. When the protective tiles are heated with electricity, they expand, especially in the direction of the plate surface, and the spacing between the protective walls decreases as the temperature increases. By making the contact surface between the wedge-shaped connector 12 and the protective tile 6 of a material with a small coefficient of friction, such as graphite, the protective tile 12
As the wedge-shaped connector 12 is pushed upward in FIG. 2, that is, toward the plasma side, with the thermal expansion of the protective tile 6, the thermal expansion of the protective tile 6 can be absorbed.
その場合、楔形接続子12の冷却基板8への取り付は方
法は、スプリングを介した機械的締結法が望ましい。楔
形接続子12は防護タイル6の防護材13を相互に電気
的に接続させるだけでなく、防護タイル6が破断したり
、冶金的締結部分が剥離した場合に防護タイルの冷却基
板8からの脱落を防止する効果をもち、炉壁の信頼性の
向上に役立つ。なお1本実施例では防護タイル6の形状
として長方形の基底面をもつ場合を示したが、他の形状
、例えば、三角形、あるいは、六角形でも同様の目的が
達せられる。また、隣接する防護タイル6間に楔形接続
子12を設置する位置は、防護材13に誘起される誘導
電流により生じる電磁力が許容レベル以下になるように
決めることが望ましい。図中15はスリット。In that case, the wedge-shaped connector 12 is preferably attached to the cooling board 8 by a mechanical fastening method using a spring. The wedge-shaped connector 12 not only electrically connects the protective material 13 of the protective tile 6 to each other, but also prevents the protective tile from falling off from the cooling board 8 if the protective tile 6 breaks or the metallurgical fastening part peels off. It has the effect of preventing this and helps improve the reliability of the furnace wall. In this embodiment, the shape of the protective tile 6 is shown as having a rectangular base surface, but the same purpose can be achieved with other shapes, such as a triangle or a hexagon. Further, it is desirable that the position where the wedge-shaped connector 12 is installed between adjacent protective tiles 6 be determined so that the electromagnetic force generated by the induced current induced in the protective material 13 is below an allowable level. 15 in the figure is a slit.
本発明を適用した実施例2において、防護材13として
比抵抗10−3Ω・口、基底面寸法10■X10a++
、厚さ10の黒鉛材を用いると、−枚の防護タイルの両
端で図った電気抵抗は10−3Ωであった。各防護タイ
ルに300人の通電を十時間行ったところ炉壁全体の温
度を600℃まで上昇させることが出来た。この場合、
加熱した防護タイルは総数二号枚で、加熱に使用した電
源容量は2000KWであった。In Example 2 to which the present invention is applied, the protective material 13 has a specific resistance of 10-3Ω, a base size of 10×10a++
When a graphite material with a thickness of 10 was used, the electrical resistance measured at both ends of the protective tile was 10 -3 Ω. When 300 people energized each protective tile for 10 hours, they were able to raise the temperature of the entire furnace wall to 600°C. in this case,
A total of No. 2 protective tiles were heated, and the power supply capacity used for heating was 2000 kW.
第3図は本発明の他の実施例を示す。防護タイル6は炭
素繊維強化炭素材、炭素繊維強化セラミックス材、また
は、金属ベリリウムで形成されている。防護タイル6は
冷却基板8に対して絶縁層14と中間材7を介して冶金
的、あるいは、機械的に締結されている。防護タイル6
にはスリット15が切り込まれており、両端に設けた接
続端子9にリード線10を接続して全体として抵抗回路
を形成する。このような防護板6に交流、又は、直流電
流を流すことにより、防護タイル6の脱ガスを効率良く
行うことが出来る。FIG. 3 shows another embodiment of the invention. The protective tile 6 is made of carbon fiber-reinforced carbon material, carbon fiber-reinforced ceramic material, or beryllium metal. The protective tile 6 is metallurgically or mechanically fastened to the cooling substrate 8 via the insulating layer 14 and the intermediate material 7. Protective tile 6
A slit 15 is cut in, and lead wires 10 are connected to connection terminals 9 provided at both ends to form a resistance circuit as a whole. By passing an alternating current or direct current through such a protection plate 6, the protection tiles 6 can be efficiently degassed.
本実施例によれば、加熱温度の調整は防護タイルに対す
る通電量によって容易に制御できるので、炉運転中の壁
面温度を最適制御することにより、プラズマと炉壁間の
水素燃料粘子の吸収・再放出過程を能動的に制御するこ
とができる。According to this embodiment, the adjustment of the heating temperature can be easily controlled by the amount of electricity applied to the protective tile, so by optimally controlling the wall surface temperature during furnace operation, the absorption of hydrogen fuel viscous between the plasma and the furnace wall can be improved. The re-release process can be actively controlled.
本発明によれば、核融合炉の起動前および稼動中におけ
る任意の時点で、最も温度を高めて脱ガス処理を行う必
要のある防護タイルの直接的加熱を行うことができる。According to the present invention, it is possible to directly heat the protective tiles that need to be degassed at the highest temperature before starting up and at any time during the operation of the fusion reactor.
第1図は本発明の一実施例の核融合炉壁の詳細な構造図
、第2図は本発明の一実施例の核融合炉壁をもつ磁場閉
じ込め型核融合炉の回転対称軸を含む縦断面図、第3図
は本発明の他の実施例の核融合炉壁の詳細図を示す。
1・・・炉壁、2・・・真空容器、4・・・トロイダル
コイル5・・・ポロイダルコイル、6・・・防護タイル
、7・・・中間材、8・・・冷却基板。Fig. 1 is a detailed structural diagram of a fusion reactor wall according to an embodiment of the present invention, and Fig. 2 includes a rotational symmetry axis of a magnetically confined fusion reactor having a fusion reactor wall according to an embodiment of the present invention. The vertical sectional view, FIG. 3, shows a detailed view of the fusion reactor wall of another embodiment of the present invention. DESCRIPTION OF SYMBOLS 1... Furnace wall, 2... Vacuum vessel, 4... Toroidal coil 5... Poloidal coil, 6... Protective tile, 7... Intermediate material, 8... Cooling board.
Claims (1)
外周に配置された磁場発生用コイル及び前記真空容器の
前記プラズマ粒子に対向する炉壁を備えたものにおいて
、 前記炉壁は前記プラズマ粒子に対向する導電性防護材層
が電気的絶縁層を介して冷却基板に接合された積層構造
をなすことを特徴とする核融合炉壁。 2、前記導電性防護材層は電気的に接続された一組以上
の抵抗回路を形成し、前記抵抗回路の両端には電圧印加
用の接続端子を設けたことを特徴とする特許請求の範囲
第1項記載の核融合炉壁。[Scope of Claims] 1. A vacuum vessel for enclosing plasma particles, a magnetic field generating coil disposed around the outer periphery of the vacuum vessel, and a furnace wall facing the plasma particles of the vacuum vessel, comprising: A fusion reactor wall characterized in that the reactor wall has a laminated structure in which a conductive protective material layer facing the plasma particles is joined to a cooling substrate via an electrically insulating layer. 2. Claims characterized in that the conductive protective material layer forms one or more sets of electrically connected resistance circuits, and connection terminals for voltage application are provided at both ends of the resistance circuits. The fusion reactor wall described in item 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62261579A JP2569078B2 (en) | 1987-10-19 | 1987-10-19 | Fusion reactor wall |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62261579A JP2569078B2 (en) | 1987-10-19 | 1987-10-19 | Fusion reactor wall |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01105190A true JPH01105190A (en) | 1989-04-21 |
| JP2569078B2 JP2569078B2 (en) | 1997-01-08 |
Family
ID=17363878
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62261579A Expired - Lifetime JP2569078B2 (en) | 1987-10-19 | 1987-10-19 | Fusion reactor wall |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2569078B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01250892A (en) * | 1988-03-31 | 1989-10-05 | Japan Atom Energy Res Inst | First wall of nuclear fusion device |
| JP2013191566A (en) * | 2003-04-16 | 2013-09-26 | Mks Instruments Inc | Toroidal low-field reactive gas and plasma source having dielectric vacuum vessel |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6251299U (en) * | 1985-09-20 | 1987-03-30 |
-
1987
- 1987-10-19 JP JP62261579A patent/JP2569078B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6251299U (en) * | 1985-09-20 | 1987-03-30 |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01250892A (en) * | 1988-03-31 | 1989-10-05 | Japan Atom Energy Res Inst | First wall of nuclear fusion device |
| JP2013191566A (en) * | 2003-04-16 | 2013-09-26 | Mks Instruments Inc | Toroidal low-field reactive gas and plasma source having dielectric vacuum vessel |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2569078B2 (en) | 1997-01-08 |
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