JPH07167972A - First wall of fusion device - Google Patents
First wall of fusion deviceInfo
- Publication number
- JPH07167972A JPH07167972A JP5314808A JP31480893A JPH07167972A JP H07167972 A JPH07167972 A JP H07167972A JP 5314808 A JP5314808 A JP 5314808A JP 31480893 A JP31480893 A JP 31480893A JP H07167972 A JPH07167972 A JP H07167972A
- Authority
- JP
- Japan
- Prior art keywords
- armor
- wall
- fusion device
- bolt
- nuclear fusion
- 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
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
- Pressure Welding/Diffusion-Bonding (AREA)
Abstract
Description
【0001】[0001]
【産業上の利用分野】本発明は、核融合装置のダイバー
タ、リミッター等の第一壁に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a first wall such as a diverter or limiter of a nuclear fusion device.
【0002】[0002]
【従来の技術】核融合装置においては、図7に示すよう
に高温、高エネルギーのプラズマ1からの高熱負荷、高
粒子負荷に対し真空境界となるような真空容器2、ブラ
ンケット又は遮蔽体等を保護する目的で、これら部材の
プラズマ側表面に第一壁3が設置される。2. Description of the Related Art In a nuclear fusion device, as shown in FIG. 7, a vacuum container 2, a blanket or a shield, which forms a vacuum boundary against a high heat load and a high particle load from a high temperature and high energy plasma 1, is provided. A first wall 3 is provided on the plasma side surface of these members for protection purposes.
【0003】ところで、金属壁がプラズマ1に直接面し
ていると、荷電交換中の中性粒子等が金属壁に入射し、
スパッタリング等の現象によって高原子番号の金属粒子
がプラズマ1へ不純物として混入し、プラズマ運転に支
障をきたす。このため、第一壁は一般に黒鉛またはセラ
ミック材のような高融点、低原子番号材を用いて構成さ
れる。When the metal wall directly faces the plasma 1, neutral particles or the like during charge exchange enter the metal wall,
Due to a phenomenon such as sputtering, metal particles having a high atomic number are mixed into the plasma 1 as impurities, which hinders the plasma operation. Therefore, the first wall is generally made of a high melting point, low atomic number material such as graphite or ceramic material.
【0004】また、第一壁3の表面の耐熱タイル(以下
アーマタイルと呼ぶ)には、プラズマ1から放射やイオ
ン、電子、中性粒子等の入射により、高熱負荷及び高粒
子負荷があり、アーマタイルは破損したり、損耗したり
するために交換する必要がある。プラズマ運転による炉
内の放射化を考え、第一壁3は遠隔操作による交換可能
な機械的接続構造が望まれる。Further, the heat-resistant tile (hereinafter referred to as an armor tile) on the surface of the first wall 3 has a high heat load and a high particle load due to the radiation from the plasma 1 and the incidence of ions, electrons, neutral particles and the like. Must be replaced due to damage or wear. Considering activation in the furnace by plasma operation, it is desirable that the first wall 3 has a mechanical connection structure that can be exchanged by remote control.
【0005】図8は従来の典型的な第一壁を示す断面図
である。図8において、アーマタイル4は非磁性鋼から
なる冷却基板5上に設けられたアーマ支持座6にアーマ
取付ボルト7を介して固定される。アーマ支持座6は一
般に冷却基板5に溶接で固着される。また、冷却基板5
にはプラズマからの入射熱負荷に対する除熱のため、冷
却水用の冷却流路8が設けられている。FIG. 8 is a sectional view showing a typical first conventional wall. In FIG. 8, the armor tile 4 is fixed to an armor support seat 6 provided on a cooling substrate 5 made of non-magnetic steel via an armor mounting bolt 7. The armor support seat 6 is generally fixed to the cooling substrate 5 by welding. In addition, the cooling substrate 5
Is provided with a cooling flow path 8 for cooling water for removing heat from the incident heat load from the plasma.
【0006】ここで、アーマタイル4及びアーマ取付ボ
ルト7は共にプラズマに面する部材のため、黒鉛又はセ
ラミック材のような高融点、低原子番号材で構成され、
図7に示すようにプラズマ1の周辺全面に配置される。Since the armor tile 4 and the armor mounting bolt 7 are members facing the plasma, they are made of a high melting point, low atomic number material such as graphite or ceramic material.
As shown in FIG. 7, it is arranged on the entire peripheral surface of the plasma 1.
【0007】一方、第一壁はプラズマからの高熱負荷を
受けるため、グラファイト、タングステン、モリブデン
等の高融点材料からなるアーマおよびプラズマからの熱
を除熱するための冷却剤流路を形成した銅又は銅合金等
の高熱伝導性材料からなるヒートシンクから構成したも
のがある。On the other hand, since the first wall receives a high heat load from the plasma, an armor made of a high melting point material such as graphite, tungsten, molybdenum and a copper having a coolant passage for removing heat from the plasma are formed. Alternatively, there is a heat sink made of a highly heat conductive material such as a copper alloy.
【0008】図9はこのような第一壁を示す断面図であ
る。図9に示す第一壁は、グラファイト又は炭素繊維複
合材(CFC)アーマ11と銅冷却管13を内蔵した銅
ヒートシンク12とを冶金的に接合した構成のもので、
両部材の接合面14がフラットな面を形成し、接合面端
部15は自由境界面となっている。また、冷却管13の
内側は除熱用に通水された冷却水内圧16を受ける構成
となっている。FIG. 9 is a sectional view showing such a first wall. The first wall shown in FIG. 9 has a configuration in which a graphite or carbon fiber composite material (CFC) armor 11 and a copper heat sink 12 containing a copper cooling tube 13 are metallurgically joined together,
The joint surface 14 of both members forms a flat surface, and the joint surface end 15 is a free boundary surface. Further, the inside of the cooling pipe 13 is configured to receive the cooling water internal pressure 16 that has been passed for removing heat.
【0009】一般にアーマ部材を構成する高融点材料は
熱膨脹率が小さく、アーマ材を接合する銅ヒートシンク
材とで熱膨脹率の差が大きい。このため、冶金的接合構
造では接合時やプラズマ熱負荷時において、接合界面近
傍に過大な熱応力が発生する。図10は図9の接合面端
部の拡大図を示すもので、上記熱応力は接合面端部15
で最大になり、接合面端部にクラック17が発生する傾
向にある。Generally, the high melting point material forming the armor member has a small coefficient of thermal expansion, and the difference in the coefficient of thermal expansion between the copper heat sink material for joining the armor material is large. Therefore, in the metallurgical joining structure, excessive thermal stress is generated near the joining interface during joining or during plasma heat load. FIG. 10 is an enlarged view of the end portion of the joint surface of FIG. 9, in which the thermal stress is 15
It becomes the maximum, and cracks 17 tend to occur at the end of the joint surface.
【0010】図11は上記の問題を解決するために考え
られた接合型第一壁の断面形状で、グラファイト又はC
FCアーマ11の中心部に円孔を設け、銅冷却管13を
挿入して冶金的に接合するものである。図11では接合
界面14が閉じているため、接合端部が構造上存在せ
ず、接合時又は負荷時の接合界面上に過大な熱応力の発
生が抑制される。ここで、図9の接合構造を“フラット
型接合構造”、図11の接合構造を“モノブロック型接
合構造”と称されている。FIG. 11 is a cross-sectional shape of the first wall of the joining type which is conceived to solve the above-mentioned problems.
A circular hole is provided in the center of the FC armor 11, and a copper cooling pipe 13 is inserted to perform metallurgical joining. In FIG. 11, since the joint interface 14 is closed, the joint end portion does not exist structurally, and excessive thermal stress is suppressed from being generated on the joint interface during joining or under load. Here, the joining structure of FIG. 9 is referred to as a “flat type joining structure”, and the joining structure of FIG. 11 is referred to as a “monoblock type joining structure”.
【0011】[0011]
【発明が解決しようとする課題】しかし、図8に示すよ
うな受熱板構造の第一壁においては、次のような問題が
考えられる。プラズマからの高熱負荷や中性子負荷によ
る核発熱によって、アーマタイル4やアーマ取付ボルト
7に入熱があると、この熱は冷却基板5上の支持座6と
アーマタイル4の接触部およびアーマ取付ボルト7のネ
ジ部との接触部より冷却基板5に伝導され、この冷却基
板5に設けられた冷却流路8に流れる冷却水により冷却
して除熱する機構となっている。However, the following problems can be considered in the first wall of the heat receiving plate structure as shown in FIG. When heat is applied to the armor tile 4 and the armor mounting bolt 7 due to nuclear heat generated by high heat load or neutron load from plasma, this heat is applied to the contact portion between the support seat 6 on the cooling substrate 5 and the armor tile 4 and the armor mounting bolt 7. It is a mechanism that conducts heat to the cooling substrate 5 from the contact portion with the screw portion, and cools and removes heat by the cooling water flowing in the cooling flow path 8 provided in the cooling substrate 5.
【0012】従って、このような除熱機構においては、
上記部材間の接触熱伝導の良好な状態もしくは熱負荷が
小さい場合には十分な冷却性能を有しているが、接触面
の接触面不具合や熱負荷が大きい場合にはアーマタイ
ル、アーマ取付ボルトの温度上昇が大きくなり、除熱の
観点から問題となる危険があった。Therefore, in such a heat removal mechanism,
It has sufficient cooling performance when the contact heat conduction between the above members is good or when the heat load is small, but when the contact surface failure of the contact surface or the heat load is large, the armor tile and the armor mounting bolt There was a danger that the temperature would increase significantly and that it would be a problem from the viewpoint of heat removal.
【0013】特に、アーマ取付ボルトの高温化はネジ部
のカジリや溶着等によってアーマタイル破損時の分解修
理が不可能となり、核融合装置の運転に大きな支障をき
たすという問題があった。In particular, there has been a problem that the high temperature of the armor mounting bolt makes it impossible to disassemble and repair the armor tile when the armor tile is damaged due to galling or welding of the screw portion, which seriously hinders the operation of the fusion device.
【0014】また、図11に示すようなモノブロック型
接合構造の第一壁においては、次のような問題が考えら
れる。今後予定される大型核融合実験炉クラスのダイバ
ータ板、第一壁の冷却水内圧16は,概ね3.5Mpa
と大きい。このため、冷却管13の冷却水内圧16によ
る応力が大きくなり、銅冷却管13の塑性変形による接
合構造体が破損に至る可能性がある。Further, in the first wall of the monoblock type joint structure as shown in FIG. 11, the following problems can be considered. The divertor plate for the large-scale fusion experimental reactor class and the cooling water internal pressure 16 of the first wall, which is planned for the future, are approximately 3.5 MPa.
And big. For this reason, the stress due to the internal pressure 16 of the cooling water in the cooling pipe 13 increases, and the joint structure may be damaged due to the plastic deformation of the copper cooling pipe 13.
【0015】また、接合時の高温により冷却管銅が軟化
してしまうため、銅冷却管の機械的強度が低下してしま
う。これは図9のフラット型接合構造の第一壁において
も同じ問題がある。Further, since the cooling pipe copper is softened by the high temperature at the time of joining, the mechanical strength of the copper cooling pipe is lowered. This has the same problem in the first wall of the flat joint structure of FIG.
【0016】そこで、熱伝導性を下げないで、高温高強
度特性を有するアルミナ、ジルコニア等の分散強化銅を
冷却管に用いることが考えられる。図12はモノブロッ
ク型接合構造の第一壁に分散強化銅冷却管13aを適用
したものである。Therefore, it is conceivable to use dispersion strengthened copper such as alumina and zirconia having high temperature and high strength characteristics in the cooling pipe without lowering the thermal conductivity. In FIG. 12, the dispersion strengthened copper cooling pipe 13a is applied to the first wall of the monoblock type joint structure.
【0017】しかし、冷却管13aの強度が高いと、接
合界面14においてグラファイト又はCFCアーマ11
への反力が大きく、グラファイト又はCFCアーマ11
側へクラック17を発生させる要因にもなる。これは逆
に冷却管強度が高く、接合時に塑性変形が生じなくな
り、グラファイト又はCFCアーマ11側へ過大な反力
がかかるためである。However, if the strength of the cooling pipe 13a is high, the graphite or CFC armor 11 is formed at the bonding interface 14.
The reaction force against is large and graphite or CFC armor 11
It also causes a crack 17 to the side. This is because, on the contrary, the strength of the cooling pipe is high, plastic deformation does not occur at the time of joining, and an excessive reaction force is applied to the graphite or CFC armor 11 side.
【0018】従って、モノブロック型接合構造の第一壁
では、接合面端部の問題、高冷却水内圧16への対策は
解決できるものの、接合時の接合材肩部18付近の接合
界面14のグラファイト又はCFCアーマ11側に発生
するクラック17の問題が新たに生じる。Therefore, in the first wall of the monoblock type joint structure, although the problem of the end portion of the joint surface and the countermeasure against the high cooling water internal pressure 16 can be solved, the joint interface 14 in the vicinity of the joint material shoulder portion 18 at the time of joining is solved. A new problem of the crack 17 generated on the graphite or CFC armor 11 side occurs.
【0019】本発明の第1の目的は、アーマタイル、ア
ーマ取付ボルトと冷却基板間の熱伝導性を向上させ、冷
却基板からの除熱効率を高めてアーマタイルやアーマ取
付ボルトの高温化を防止できる安全性、信頼性の高い核
融合装置の第一壁を提供することにある。A first object of the present invention is to improve the thermal conductivity between the armor tiles, the armor mounting bolts and the cooling board, improve the efficiency of removing heat from the cooling board, and prevent the armature tiles and the armor mounting bolts from becoming hot. It is to provide the first wall of a fusion device with high reliability and reliability.
【0020】また、本発明の第2の目的は、グラファイ
トアーマとその中心部に挿入される冷却管との接合時に
アーマが破損することのない構造上の強度に対する信頼
性の向上を図ることのできる核融合装置の第一壁を提供
することにある。A second object of the present invention is to improve the reliability of the structural strength such that the armor will not be damaged when the graphite armor and the cooling pipe inserted in the center of the graphite armor are joined. It is to provide the first wall of a possible fusion device.
【0021】[0021]
【課題を解決するための手段】本発明は上記の目的を達
成するため、次のような手段により核融合装置の第一壁
を構成するものである。 (1)アーマタイルを冷却基板上に設けられたアーマ支
持座にアーマ取付ボルトにより固定する構造の核融合装
置の第一壁において、前記アーマ取付ボルトの頭部背面
およびネジ部内径に置ハンダを埋設した溝を設け、ボル
ト締結時に前記アーマ取付ボルトを加熱して前記置ハン
ダを溶融させることにより、前記アーマタイルとボルト
頭部およびボルトネジ部と前記アーマ支持座とを接着す
るようにしたものである。 (2)また、上記構成のアーマ取付ボルトの中心部に部
材接触面近傍の残留ガスを抜くための通し穴を軸方向に
設けたものである。 (3)グラファイトまたは炭素繊維複合材(CFC)ア
ーマの中心部に有する穴に高温高強度の分散強化銅から
なる冷却管を挿入し、両者を冶金的に接合する構造の核
融合装置の第一壁において、前記グラファイト又はCF
Cアーマと冷却管との間に熱変形空間を有する軟化銅緩
衝材を設けて冶金的に接合したものである。In order to achieve the above object, the present invention constitutes the first wall of a nuclear fusion device by the following means. (1) In the first wall of the nuclear fusion device having a structure in which the armor tile is fixed to the armor support seat provided on the cooling board with the armor mounting bolt, the solder is embedded on the back surface of the head of the armor mounting bolt and the inner diameter of the screw part. When the bolts are fastened, the armor mounting bolts are heated to melt the placement solder, thereby bonding the armature tiles to the bolt heads, the bolt screw portions, and the armor support seats. (2) Further, a through hole for removing residual gas in the vicinity of the member contact surface is provided in the axial direction at the central portion of the armor mounting bolt having the above-mentioned configuration. (3) First of the nuclear fusion device having a structure in which a cooling pipe made of high temperature and high strength dispersion strengthened copper is inserted into a hole provided in the center of a graphite or carbon fiber composite material (CFC) armor, and both are metallurgically bonded. In the wall, said graphite or CF
A softened copper buffer material having a thermal deformation space is provided between the C armor and the cooling pipe and metallurgically bonded.
【0022】[0022]
【作用】上記(1)のような構成の核融合装置の第一壁
にあっては、アーマタイルのボルト締結後、ボルト頭部
を加熱するとボルト頭部背面およびネジ内径部に設けら
れた溝内の置ハンダが溶融し、ボルト背面およびネジス
パイラル接触面上に流れ、ボルト頭部背面とアーマタイ
ル間およびボルトネジ部とアーマ支持座のネジ穴との接
触面が接着する。従って、アーマタイル、アーマ取付ボ
ルトがプラズマより受ける熱は上記接着面を介して冷却
基板へ熱伝導し、冷却基板内の冷却水により除熱され
る。In the first wall of the nuclear fusion device configured as described above in (1), when the bolt head is heated after the bolt of the armature is fastened, the inside of the groove provided in the bolt head rear surface and the screw inner diameter portion Placed solder melts and flows on the back surface of the bolt and the contact surface of the screw spiral, and the contact surface between the back surface of the bolt head and the armature and the contact surface between the bolt screw portion and the screw hole of the armor support seat are bonded. Therefore, the heat that the armature tile and the armor mounting bolt receive from the plasma is conducted to the cooling substrate through the adhesive surface and is removed by the cooling water in the cooling substrate.
【0023】また、上記(2)のようにボルト締結時に
ハンダ埋設溝内の置ハンダの流れを良好にするため、ボ
ルト中心部に軸方向に抜ける通し穴を設けることによ
り、アーマ支持座、ボルトネジ接触面のガス抜きが容易
であり、ハンダの接触面上の流れを促進させることが可
能となる。Further, as described in the above (2), in order to improve the flow of the placed solder in the solder embedding groove at the time of fastening the bolt, a through hole is formed in the center of the bolt so as to be axially pulled out. The contact surface can be easily degassed, and the flow on the contact surface of the solder can be promoted.
【0024】上記(3)のような構成の核融合装置の第
一壁にあっては、グラファイト又はCFCアーマの中心
部に有する穴内に分散強化銅からなる冷却管を配置して
高冷却水内圧に耐える構造とし、グラファイト又はCF
Cアーマと冷却管との間に熱変形空間を有する軟化銅緩
衝材を設けるようにしたので、負荷時の高冷却内圧に耐
え、且つ接合界面に過大な熱応力がかかることなく、グ
ラファイト又はCFCアーマが破損するようなことがな
くなり、信頼性の高い機械的強度を得ることが可能とな
る。In the first wall of the nuclear fusion device having the structure as described in (3) above, a cooling pipe made of dispersion strengthened copper is arranged in a hole provided at the center of graphite or CFC armor, and high internal pressure of cooling water is provided. Resistant to structure, graphite or CF
Since a softened copper buffer material having a thermal deformation space is provided between the C armor and the cooling pipe, it can withstand high cooling internal pressure under load and does not receive excessive thermal stress on the bonding interface, and graphite or CFC The armor will not be damaged, and reliable mechanical strength can be obtained.
【0025】[0025]
【実施例】以下本発明の実施例を図面を参照して説明す
る。図1は本発明による核融合装置の第一壁の第1の実
施例を示す断面図である。図1において、21はボルト
頭部およびネジ部を挿入し得るボルト挿入穴21aを有
するアーマタイル、22は内部に冷却流路23が形成さ
れ、且つ板面よりネジ穴を有するアーマ支持座24を突
出させて設けられた冷却基板である。また、25はアー
マタイル21を冷却基板22のアーマ支持座24に固定
するためのアーマ取付ボルトで、このアーマ取付ボルト
25の中心部に軸方向に抜ける通し穴26が設けられて
いる。Embodiments of the present invention will be described below with reference to the drawings. FIG. 1 is a sectional view showing a first embodiment of the first wall of the nuclear fusion device according to the present invention. In FIG. 1, reference numeral 21 denotes an armor tile having a bolt insertion hole 21a into which a bolt head and a screw portion can be inserted, and 22 denotes an armor support seat 24 having a cooling hole 23 formed therein and having a screw hole projected from a plate surface. This is the cooling substrate provided. Further, reference numeral 25 is an armor mounting bolt for fixing the armor tile 21 to the armor support seat 24 of the cooling board 22, and a through hole 26 is formed at the center of the armor mounting bolt 25 so as to be axially removed.
【0026】このような冷却基板22にアーマタイル2
1を取付けるには、図2に詳細を示すようにアーマ取付
ボルト25の頭部背面とネジ内径部、さらにアーマ支持
座24のタイル取付面に置ハンダ27を埋設したハンダ
埋込溝28をそれぞれ設け、アーマタイル21のボルト
挿入穴21aよりアーマ支持座24のネジ穴にアーマ取
付ボルト25を挿入して締付ける。The armor tile 2 is attached to such a cooling substrate 22.
As shown in detail in FIG. 2, the head back surface and the screw inner diameter portion of the armor mounting bolt 25, and the solder embedding groove 28 in which the mounting solder 27 is embedded are further provided on the tile mounting surface of the armor support seat 24. The armature mounting bolt 25 is provided and inserted into the screw hole of the armor support seat 24 through the bolt insertion hole 21a of the armature tile 21 and tightened.
【0027】この場合、ボルト締結時にアーマ取付ボル
ト25を加熱して置ハンダ27を溶融させ、部材間のハ
ンダ接着面29にハンダを流し込んでアーマタイル21
とボルト頭部、ボルトネジ部とアーマ支持座24のネジ
穴部およびアーマタイル21とアーマ支持座24の取付
面の各部材間をそれぞれ接着する。In this case, when the bolts are fastened, the armor mounting bolts 25 are heated to melt the placement solder 27, and the solder is poured into the solder bonding surface 29 between the members so that the armor tile 21
The bolt head portion, the bolt screw portion, the screw hole portion of the armor support seat 24, and the respective members on the mounting surface of the armature tile 21 and the armor support seat 24 are bonded together.
【0028】また、このとき部材接触面近傍の残留ガス
はアーマ取付ボルト25の中心部に有する通し穴26よ
りガス抜きが行われ、置ハンダ27の部材接触面への流
れが良好になる。Further, at this time, the residual gas in the vicinity of the member contact surface is degassed from the through hole 26 provided at the center of the armor mounting bolt 25, so that the flow of the placing solder 27 to the member contact surface becomes good.
【0029】このように上記第1の実施例においては、
アーマ取付ボルト25の頭部背面とネジ内径部およびア
ーマ支持座24のタイル取付面に置ハンダ27を埋設し
たハンダ埋込溝28をそれぞれ設けておき、アーマタイ
ル21を冷却基板22のアーマ支持座24にアーマ取付
ボルト25により締付けて固定する際に、アーマ取付ボ
ルト25を加熱して各部材接触面間にハンダを流し込ん
でアーマタイル21とボルト頭部、ボルトネジ部とアー
マ支持座24のネジ穴部およびアーマタイル21とアー
マ支持座24の取付面の各部材間をそれぞれ接着するよ
うにしたものである。As described above, in the first embodiment,
A solder embedding groove 28 in which a mounting solder 27 is embedded is provided in the head rear surface of the armor mounting bolt 25, the screw inner diameter portion, and the tile mounting surface of the armor support seat 24, and the armor tile 21 is mounted on the armor support seat 24 of the cooling board 22. When the armor mounting bolt 25 is tightened and fixed to the armor mounting bolt 25, the armor mounting bolt 25 is heated and a solder is poured between the contact surfaces of the respective members so that the armor tile 21 and the bolt head portion, the bolt screw portion and the screw hole portion of the armor support seat 24, and The armature tile 21 and the armor support seat 24 are attached to each other at their mounting surfaces.
【0030】従って、部材間の熱的接触および接着が強
固になり、アーマタイル21、アーマ取付ボルト25と
冷却基板22の熱伝導特性を高めることができるので、
プラズマよりアーマタイル21、アーマ取付ボルト25
が熱せられても、その熱は上記ハンダ接着面を介して冷
却基板22へ熱伝導機構にて移動し、冷却基板22内の
冷却流路23に流れる冷却水により除熱され、第一壁構
造の除熱効率を向上させることができる。これにより上
記第一壁部材の高温化を防止し、安全性、信頼性の向上
を図ることができる。Therefore, the thermal contact and adhesion between the members are strengthened, and the heat conduction characteristics of the armor tile 21, the armor mounting bolt 25 and the cooling substrate 22 can be enhanced,
Armature tile 21 and armor mounting bolt 25 from plasma
Even if the heat is applied, the heat moves to the cooling board 22 through the solder bonding surface by the heat conduction mechanism and is removed by the cooling water flowing in the cooling flow path 23 in the cooling board 22. The heat removal efficiency of can be improved. As a result, it is possible to prevent the temperature of the first wall member from rising and to improve safety and reliability.
【0031】また、アーマタイル分解時には、ボルト頭
部を加熱することにより接着面上のハンダ層を溶融し、
アーマタイル21,アーマ取付ボルト25を簡単に取外
すことができる。When the armature is disassembled, the bolt head is heated to melt the solder layer on the adhesive surface,
The armor tile 21 and the armor mounting bolt 25 can be easily removed.
【0032】さらに、ボルト締結時にハンダ埋設溝28
内の置ハンダ27の流れを良好にするため、ボルト中心
部に通し穴26が設けられているので、アーマ支持座2
4、ボルトのネジ接触面のガス抜きを容易にし、ハンダ
の接触面上の流れを促進させることができる。Further, when the bolt is fastened, the solder burying groove 28
Since the through hole 26 is provided in the center of the bolt in order to improve the flow of the placed solder 27 inside, the armor support seat 2
4. It is possible to facilitate the degassing of the screw contact surface of the bolt and promote the flow on the contact surface of the solder.
【0033】次に本発明による各融合装置の第一壁の第
2の実施例を図3および図4を参照して説明する。図3
において、31は中心部に円形の穴32を有するグラフ
ァイト又はCFCアーマで、このグラファイト又はCF
Cアーマ31の穴32内に分散強化銅からなる冷却管3
3を挿入すると共に、グラファイト又はCFCアーマ3
1と冷却管33との間に周方向に複数に分割された軟化
銅緩衝材34を相互間にスリット35をそれぞれ存して
配置し、グラファイト又はCFCアーマ31、分散強化
銅の冷却管33および軟化銅緩衝材34の間を冶金的に
接合する。Next, a second embodiment of the first wall of each fusion device according to the present invention will be described with reference to FIGS. 3 and 4. Figure 3
In, 31 is a graphite or CFC armor having a circular hole 32 in the center thereof.
Cooling pipe 3 made of dispersion strengthened copper in hole 32 of C armor 31
3 and insert graphite or CFC armor 3
1 and the cooling pipe 33, a plurality of softened copper buffers 34 divided in the circumferential direction are arranged with slits 35 between each, and graphite or CFC armor 31, dispersion strengthened copper cooling pipe 33 and The softened copper buffer material 34 is metallurgically bonded.
【0034】図4は図3の接合体肩部36の拡大図を示
すもので、冶金的接合界面37はグラファイト又はCF
Cアーマ31と軟化銅緩衝材34との間および軟化銅緩
衝材34と分散強化銅冷却管33との間に生じている。FIG. 4 is an enlarged view of the shoulder portion 36 of the joined body of FIG. 3, in which the metallurgical joining interface 37 is made of graphite or CF.
It occurs between the C armor 31 and the softened copper buffer material 34 and between the softened copper buffer material 34 and the dispersion strengthened copper cooling pipe 33.
【0035】このような構成の核融合装置の第一壁とす
れば、グラファイト又はCFCアーマ31の穴32内に
分散強化銅冷却管33を配設しているので、接合時に冷
却管が軟化することはなく、高冷却水による内圧に耐え
る構造となし得る。In the case of the first wall of the nuclear fusion device having such a structure, since the dispersion strengthened copper cooling pipe 33 is arranged in the hole 32 of the graphite or CFC armor 31, the cooling pipe is softened at the time of joining. However, the structure can withstand the internal pressure of the high cooling water.
【0036】また、グラファイト又はCFCアーマ31
と分散強化銅冷却管33との間に周方向に複数に分割さ
れ、且つ分割相互間にスリット35が存するように軟化
銅緩衝材34を配置するようにしているので、グラファ
イト又はCFCアーマ31と分散強化銅冷却管33間の
熱膨脹係差による熱応力に伴うグラファイト又はCFC
アーマ31側への反力を銅緩衝材の塑性変形促進によっ
て減少させることができる。Also, graphite or CFC armor 31
And the dispersion-strengthened copper cooling pipe 33 are divided into a plurality of pieces in the circumferential direction, and the softening copper buffer material 34 is arranged so that the slits 35 exist between the divided portions. Graphite or CFC accompanying thermal stress due to thermal expansion difference between dispersion strengthened copper cooling tubes 33
The reaction force to the armor 31 side can be reduced by promoting the plastic deformation of the copper cushioning material.
【0037】このとき、周方向に分割された軟化銅緩衝
材間のスリットの存在によって緩衝材の塑性変形を拘束
することなく促進され、グラファイト又はCFCアーマ
31側の接合界面近傍において、グラファイト又はCF
Cアーマ31側への反力を低減でき、アーマ材に過大な
反力が掛かることがなく、アーマが破損することはな
い。At this time, the presence of the slits between the softened copper buffer materials divided in the circumferential direction promotes the plastic deformation of the buffer material without restraining it, and the graphite or CF near the bonding interface on the graphite or CFC armor 31 side.
The reaction force to the C armor 31 side can be reduced, an excessive reaction force is not applied to the armor material, and the armor is not damaged.
【0038】このように上記第2の実施例においては、
グラファイト又はCFCアーマ31の中心部に有する円
形の穴32内に分散強化銅からなる冷却管33を配置し
て高冷却水内圧に耐える構造とし、グラファイト又はC
FCアーマ31と冷却管33との間に周方向に複数に分
割された軟化銅緩衝材34を相互間にスリット35をそ
れぞれ存して設けるようにしたので、負荷時の高冷却内
圧に耐え、且つ接合界面に過大な熱応力がかかることな
く、グラファイト又はCFCアーマ31が破損に至らる
ことのない強度上信頼性の高い第一壁となし得る。As described above, in the second embodiment,
A cooling pipe 33 made of dispersion-strengthened copper is arranged in a circular hole 32 provided at the center of the graphite or CFC armor 31 so as to withstand a high internal pressure of cooling water.
Between the FC armor 31 and the cooling pipe 33, the softened copper buffer material 34 divided into a plurality in the circumferential direction is provided with the slits 35 between each other, so that it can withstand a high cooling internal pressure at the time of loading, In addition, the graphite or CFC armor 31 can be formed as a highly reliable first wall with high strength without applying excessive thermal stress to the bonding interface and causing no damage.
【0039】なお、上記実施例では軟化銅緩衝材34を
相互間にスリット35をそれぞれ存して設けるようにし
たが、図5に示す第3の実施例のように軟化銅緩衝材3
4の周方向に沿って複数個の溝38を半径方向に設けて
接合面、特にグラファイト又はCFCアーマ31と軟化
銅緩衝材34との間の接合面に作用するアーマ熱応力を
緩和させることができる。Although the softened copper buffer material 34 is provided with the slits 35 between each other in the above embodiment, the softened copper buffer material 3 is provided as in the third embodiment shown in FIG.
A plurality of grooves 38 are provided in the radial direction along the circumferential direction of 4 to alleviate the armor thermal stress acting on the joint surface, particularly the joint surface between the graphite or CFC armor 31 and the softened copper buffer material 34. it can.
【0040】また、図6に示す第4の実施例のようによ
うに軟化銅緩衝材領域として銅製金網状の銅メッシュ3
9にして熱熱変形空間を確保することによって熱変形を
容易にすることにより、アーマ熱応力を緩和することが
できる。Further, as in the fourth embodiment shown in FIG. 6, as the softened copper buffer material region, the copper wire mesh copper mesh 3 made of copper is used.
Armature thermal stress can be relieved by making thermal deformation easy by making it 9 and ensuring a thermal deformation space.
【0041】[0041]
【発明の効果】以上述べたように本発明によれば、機械
的強度に優れ、且つ信頼性の高い核融合装置の第一壁を
提供することができる。As described above, according to the present invention, it is possible to provide the first wall of the nuclear fusion device having excellent mechanical strength and high reliability.
【図1】本発明による核融合装置の第一壁の第1の実施
例を示す断面図。FIG. 1 is a sectional view showing a first embodiment of the first wall of the nuclear fusion device according to the present invention.
【図2】同実施例におけるアーマ取付ボルトとアーマ支
持座間の接続構造を詳細に示す断面図。FIG. 2 is a cross-sectional view showing in detail a connection structure between an armor mounting bolt and an armor support seat in the same embodiment.
【図3】本発明による核融合装置の第一壁の第2の実施
例を示す断面図。FIG. 3 is a sectional view showing a second embodiment of the first wall of the nuclear fusion device according to the present invention.
【図4】同実施例における接合体肩部を拡大して示す断
面図。FIG. 4 is an enlarged sectional view showing a shoulder portion of the joined body in the embodiment.
【図5】本発明の第3の実施例における接合体肩部を拡
大して示す断面図。FIG. 5 is an enlarged sectional view showing a shoulder portion of a joined body according to a third embodiment of the present invention.
【図6】本発明の第4の実施例における接合体肩部を拡
大して示す断面図。FIG. 6 is an enlarged sectional view showing a shoulder portion of a joined body according to a fourth embodiment of the present invention.
【図7】トーラス型核融合装置における第一壁周辺の炉
本体の模式図。FIG. 7 is a schematic diagram of the reactor body around the first wall in the torus fusion device.
【図8】従来の機械的締結構造の第一壁を示す断面図。FIG. 8 is a sectional view showing a first wall of a conventional mechanical fastening structure.
【図9】従来のフラット型接合構造の第一壁を示す断面
図。FIG. 9 is a cross-sectional view showing a first wall of a conventional flat type joint structure.
【図10】同第一壁の接合面端部を拡大して示す断面
図。FIG. 10 is an enlarged cross-sectional view showing an end portion of the joint surface of the first wall.
【図11】従来のモノブロック型接合構造の第一壁を示
す断面図。FIG. 11 is a cross-sectional view showing a first wall of a conventional monoblock type joint structure.
【図12】同第一壁の接合面端部を拡大して示す断面
図。FIG. 12 is an enlarged cross-sectional view showing a joint surface end portion of the first wall.
21…アーマタイル、21a…挿入穴、22…冷却基
板、23…冷却水路、24…アーマ支持座、25…アー
マ取付ボルト、26…通し穴、27…置ハンダ、28…
ハンダ埋込溝、29…接着面、31…グラファイト又は
CFCアーマ、32…円形の穴、33…分散強化銅から
なる冷却管、34…軟化銅緩衝材、35…スリット、3
6…溝。21 ... Armor tile, 21a ... Insertion hole, 22 ... Cooling board, 23 ... Cooling channel, 24 ... Armor support seat, 25 ... Armor mounting bolt, 26 ... Through hole, 27 ... Placed solder, 28 ...
Solder embedding groove, 29 ... Adhesive surface, 31 ... Graphite or CFC armor, 32 ... Circular hole, 33 ... Cooling tube made of dispersion strengthened copper, 34 ... Softened copper buffer material, 35 ... Slit, 3
6 ... groove.
Claims (7)
アーマ支持座にアーマ取付ボルトにより固定する構造の
核融合装置の第一壁において、前記アーマ取付ボルトの
頭部背面およびネジ部内径に置ハンダを埋設した溝を設
け、ボルト締結時に前記アーマ取付ボルトを加熱して前
記置ハンダを溶融させることにより、前記アーマタイル
とボルト頭部およびボルトネジ部と前記アーマ支持座と
を接着するようにしたことを特徴とする核融合装置の第
一壁。1. In a first wall of a nuclear fusion device having a structure in which an armor tile is fixed to an armor support seat provided on a cooling board by an armor mounting bolt, a solder is placed on a back surface of the head of the armor mounting bolt and an inner diameter of a screw part. By providing a groove in which the armor mounting bolt is melted by heating the armor mounting bolt when fastening the bolt, the armor tile and the bolt head and the bolt screw portion and the armor support seat are bonded together. The first wall of the characteristic fusion device.
近傍の残留ガスを抜くための通し穴を軸方向に設けたこ
とを特徴とする請求項1に記載の核融合装置の第一壁。2. The first wall of the nuclear fusion device according to claim 1, wherein a through hole for removing residual gas in the vicinity of the member contact surface is provided in the central portion of the armor mounting bolt in the axial direction.
持座の取付面に置ハンダを埋込んだ溝を設けたことを特
徴とする請求項1に記載の核融合装置の第一壁。3. The first wall of the nuclear fusion device according to claim 1, wherein the mounting surface of the armor support seat, which comes into contact with the back surface of the armor tile, is provided with a groove having embedded solder.
FC)アーマの中心部に有する穴に高温高強度の分散強
化銅からなる冷却管を挿入し、両者を冶金的に接合する
構造の核融合装置の第一壁において、前記グラファイト
又はCFCアーマと冷却管との間に熱変形空間を有する
軟化銅緩衝材を設けて冶金的に接合したことを特徴とす
る核融合装置の第一壁。4. A graphite or carbon fiber composite material (C
(FC) A cooling tube made of dispersion-strengthened copper having high temperature and high strength is inserted into a hole in the center of the armor, and the graphite or CFC armor is cooled in the first wall of the fusion device having a structure in which both are metallurgically joined. A first wall of a nuclear fusion device, characterized in that a softened copper buffer material having a thermal deformation space is provided between the pipe and the metallurgical joint.
且つ分割相互間にスリットを設けて熱変形空間としたこ
とを特徴とする請求項1に記載の核融合装置の第一壁。5. A soft copper buffer material is divided into a plurality of pieces in the circumferential direction,
The first wall of the nuclear fusion device according to claim 1, wherein a slit is provided between the divisions to form a thermal deformation space.
欠溝を径方向に設けて熱変形空間としたことを特徴とす
る請求項1に記載の核融合装置の第一壁。6. The first wall of the nuclear fusion device according to claim 1, wherein a soft copper buffer material is provided in the radial direction with a plurality of notches along the circumferential direction to form a thermal deformation space.
設けて熱変形空間を確保するようにしたことを特徴とす
る請求項1に記載の核融合装置の第一壁。7. The first wall of the nuclear fusion device according to claim 1, wherein a copper wire mesh copper mesh is provided in the buffer material region to secure a heat deformation space.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5314808A JPH07167972A (en) | 1993-12-15 | 1993-12-15 | First wall of fusion device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5314808A JPH07167972A (en) | 1993-12-15 | 1993-12-15 | First wall of fusion device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH07167972A true JPH07167972A (en) | 1995-07-04 |
Family
ID=18057853
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5314808A Pending JPH07167972A (en) | 1993-12-15 | 1993-12-15 | First wall of fusion device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH07167972A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007155737A (en) * | 2005-12-06 | 2007-06-21 | Plansee Se | First wall component with tube segment |
| WO2014185476A1 (en) * | 2013-05-16 | 2014-11-20 | 川崎重工業株式会社 | Heat receiving tile formed from carbon fiber composite material and method for producing same |
| WO2015119187A1 (en) * | 2014-02-05 | 2015-08-13 | 川崎重工業株式会社 | Carbon-fiber-composite heat-collecting tile and method for producing same |
| CN110648769A (en) * | 2018-06-27 | 2020-01-03 | 核工业西南物理研究院 | A first wall structure for the strong field side of a tokamak device |
| CN114373557A (en) * | 2021-12-17 | 2022-04-19 | 中国科学院合肥物质科学研究院 | Flat target plate for fusion device ultrahigh heat load component and processing method thereof |
-
1993
- 1993-12-15 JP JP5314808A patent/JPH07167972A/en active Pending
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007155737A (en) * | 2005-12-06 | 2007-06-21 | Plansee Se | First wall component with tube segment |
| KR101298346B1 (en) * | 2005-12-06 | 2013-08-20 | 플란제 에스이 | First-wall component with tube segment |
| WO2014185476A1 (en) * | 2013-05-16 | 2014-11-20 | 川崎重工業株式会社 | Heat receiving tile formed from carbon fiber composite material and method for producing same |
| JP2014224730A (en) * | 2013-05-16 | 2014-12-04 | 川崎重工業株式会社 | Heat receiving tile made of carbon fiber composite material |
| US10101094B2 (en) | 2013-05-16 | 2018-10-16 | Kawasaki Jukogyo Kabushiki Kaisha | Heat receiving tile formed of carbon fiber composite material and method of manufacturing the same |
| WO2015119187A1 (en) * | 2014-02-05 | 2015-08-13 | 川崎重工業株式会社 | Carbon-fiber-composite heat-collecting tile and method for producing same |
| JP2015148475A (en) * | 2014-02-05 | 2015-08-20 | 川崎重工業株式会社 | Carbon fiber composite heat-receiving tile and method for manufacturing the same |
| US10024605B2 (en) | 2014-02-05 | 2018-07-17 | Kawasaki Jukogyo Kabushiki Kaisha | Heat receiving tile formed of carbon fiber composite material and method of manufacturing the same |
| CN110648769A (en) * | 2018-06-27 | 2020-01-03 | 核工业西南物理研究院 | A first wall structure for the strong field side of a tokamak device |
| CN110648769B (en) * | 2018-06-27 | 2024-06-11 | 核工业西南物理研究院 | First wall structure for strong field side of tokamak device |
| CN114373557A (en) * | 2021-12-17 | 2022-04-19 | 中国科学院合肥物质科学研究院 | Flat target plate for fusion device ultrahigh heat load component and processing method thereof |
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