JPS59170787A - Vacuum vessel device of nuclear fusion device - Google Patents

Vacuum vessel device of nuclear fusion device

Info

Publication number
JPS59170787A
JPS59170787A JP58043118A JP4311883A JPS59170787A JP S59170787 A JPS59170787 A JP S59170787A JP 58043118 A JP58043118 A JP 58043118A JP 4311883 A JP4311883 A JP 4311883A JP S59170787 A JPS59170787 A JP S59170787A
Authority
JP
Japan
Prior art keywords
bellows
vacuum vessel
protective plate
nuclear fusion
support ring
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
JP58043118A
Other languages
Japanese (ja)
Inventor
大森　順次
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP58043118A priority Critical patent/JPS59170787A/en
Publication of JPS59170787A publication Critical patent/JPS59170787A/en
Pending legal-status Critical Current

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

  • Lining Or Joining Of Plastics Or The Like (AREA)
  • Secondary Cells (AREA)
  • Discharge Heating (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】 〔発明の１部術分野〕 本発明は核融合装置の真空容器装置に関する。[Detailed description of the invention] [Part 1 technical field of invention] The present invention relates to a vacuum vessel device for a nuclear fusion device.

〔発明の技術的背景とその間線点」 トカマク型核融合装置の円環状の具窒容器は、ボロイダ
ルコイルによるプラズマ゛屯流立上げのために、トロイ
ダル方向にある値以上の電流の抵抗値を有する必要があ
る。烏抵抗を得るためには、従来、第１図のように、円
環状の具空谷器（１）をトロイダル方向に複数１固（二
分割し、分゛θ」部をベローズ（２）で恢統Ｔるか、ま
たは第２図のように、分割した真富谷器（１）の間をベ
ローズ（２）の外周を覆うような円（資）体（１ａ）を
真空容器から突出し、セラミック等の絶縁物（３）を介
して連結し、所要の抵抗値になるようにしていた。[Technical Background of the Invention and Intervening Points] The annular nitrogen container of a tokamak-type nuclear fusion device has a resistance value greater than a certain value in the toroidal direction in order to generate a plasma torrent using a voloidal coil. It is necessary to have In order to obtain the crow resistance, conventionally, as shown in Fig. 1, a plurality of annular hollow troughs (1) are fixed in the toroidal direction (divided into two, and the divided "θ" part is used with a bellows (2). Or as shown in Figure 2, a circular body (1a) that covers the outer periphery of the bellows (2) is protruded between the divided Matomiya ware (1) from the vacuum container, and a ceramic etc. They were connected through an insulator (3) to obtain the required resistance value.

ベローズには、一般に成形ベローズと浴接ベローズの２
種類があり、何れも初版で製作する。トーラストロイダ
ル方向の一周抵抗値は、プラズマの抵抗値に比し十分大
きいことが必要であって、ベローズは板厚の軸内化とベ
ローズのトロイダル方向の総延長を長くするように、山
数の増加や山１１４】さの増大が求められて、ベローズ
（２）の強度に大きな影響を及ぼしている。核融合装置
の真空容器には、大気圧による荷重の外に、各コイルの
通電開始時や事故時、およびプラズマの異常消砥時に真
空容器（１）に崗竜流が流れて、この電流と周囲の６ｉ
〈湯との鎖交により真空容器（１）に大きな電磁力が働
く。この電磁力は装置の大形化に伴って大きくなって、
ベローズの強度は厳しいものとなっている。第３図は第
２図の分割部の横断面図で、従来ｂｌＪの一つである。There are generally two kinds of bellows: molded bellows and bath-welded bellows.
There are different types, all of which are first editions. The one-round resistance value in the toroidal direction needs to be sufficiently larger than the plasma resistance value, and the number of ridges of the bellows is designed so that the plate thickness is within the axis and the total extension of the bellows in the toroidal direction is lengthened. An increase in the height and height of the bellows (2) is required, and this has a great effect on the strength of the bellows (2). In addition to the load due to atmospheric pressure, the vacuum vessel of a nuclear fusion device is subject to a current and current flowing through the vacuum vessel (1) at the start of energization of each coil, in the event of an accident, and during abnormal plasma extinguishing. surrounding 6i
<A large electromagnetic force acts on the vacuum container (1) due to the linkage with the hot water. This electromagnetic force increases as the device becomes larger,
The strength of the bellows is strict. FIG. 3 is a cross-sectional view of the divided portion of FIG. 2, which is one of the conventional BLJs.

ベローズ（２）は、いくつかの山をまとめて、円筒体（
１ａ）から絶縁物（４）を介して取り付けられた支持リ
ング（５）によって支持固定しである。べＵ−ズ（２）
にかかる荷重は、一般にベローズ（２）の自交″ｌ＋ｊ
の溶接部で支持することになるため、この溶接部の応力
が非常に高くなる難点がある。The bellows (2) is a cylindrical body (
It is supported and fixed by a support ring (5) attached from 1a) through an insulator (4). BeUs (2)
Generally, the load applied to the bellows (2) is
Since it is supported by the welded part, the stress in this welded part becomes extremely high.

又、真、空茶５（１）には、プラズマからベローズ（２
）へ・・）輻射熱を防ぐため保護板（６）が設けである
。保護板（０）は、輻射熱を支持具（６ａ）を介して真
空容器（１）に伝んるため一般に金属製であり、第３図
に示した構造によると保護板（６）の長さは、ベローズ
長の１／２は必要である。このように保護板（（）１の
長さが長いということは、保護板（６）の支持部の熱負
荷が大さくなって飽和し保護板（６）のイ晶度上昇が大
きくなるはかりでなく、プラズマの屁常ｉｆ’ｉ　ｒＪ
ｋ時等に保護板（６）に藺電流が流れて′電磁力を生じ
、その支持が鐘しくなる。In addition, for Shin and Kucha 5 (1), bellows (2
)...) A protective plate (6) is provided to prevent radiant heat. The protection plate (0) is generally made of metal because it transmits radiant heat to the vacuum vessel (1) via the support (6a), and according to the structure shown in Fig. 3, the length of the protection plate (6) is , 1/2 of the bellows length is required. In this way, the long length of the protective plate (()1) means that the heat load on the support part of the protective plate (6) becomes large and saturates, resulting in a large increase in the crystallinity of the protective plate (6). It's not a plasma fart if'i rJ
At time 6, a current flows through the protection plate (6) and an electromagnetic force is generated, which makes the support stiffer.

さらに、真空容器（１）は制真空を侍るために、ベーキ
ングが行なわれるがベーキングの加熱・？′、コ却時に
おいて、ベローズ（２）は他の’ｄ　Ｋｉ　ｈ分に比べ
て板厚か格段に博いため熱伝棉が悪く、ベローズ内で大
きな温度差を生じて熱応力を生ずる。このため、加熱・
冷却の迷度は、ベローズ内のｔ晶曳ノ、−が計容される
４置忘丁となるよう（只ン入める必要があるのでベーキ
ングＮ開が非常に長くなるという欠点があった。Furthermore, the vacuum container (1) is subjected to baking in order to protect it from the vacuum, but what about the heating of the baking? During cooling, the bellows (2) is much thicker than the other 'd Ki h parts, so heat transfer is poor, and a large temperature difference occurs within the bellows, causing thermal stress. For this reason, heating and
The degree of inconsistency in cooling was such that the temperature of the t-crystals in the bellows was measured in 4 positions (there was a drawback that baking time was very long because it was necessary to insert the t-crystal in the bellows). .

〔発明の目的〕[Purpose of the invention]

本弁明の目的は真空容器の分割部に作ハ」する熱応力や
振動応力を低減させ伯ね性の商い核６１合装置の真空容
器装置を提供することにある。The purpose of the present invention is to provide a vacuum container device that reduces the thermal stress and vibration stress generated in the divided portions of the vacuum container and is resistant to damage.

〔発明の概要〕[Summary of the invention]

上記目的を構成するため（二、本発明においては、周方
向に１１Ｙ１隙を伺する分割部を設けこの分４ｉ’１部
に絶縁物を介在させて一体的に締結した円環状の與窒容
器と、上泥分λり部の内＋ｑ側をシールするベローズと
、これら真空容器とベローズとのＰ１周面を覆いプラズ
マからの輻射熱を阻止する保護板とを備えた（〕・：融
合装置し、の具窒容器装め、において、前記分割部に複
数筒の環状板の支持リングを事ねて介装し、保護板の該
分１４．．１１．九に対向する部位を軸方向１’：　＃
’ｉｌ１分して自弓設し、これらの保諌板片を大々上記
支持リングに固定するとともに前記ベローズを・夫々の
保１．ψ板片にｆｉｌｌ　イＵ　シて構成したことを特
徴とＴるυ融合装め′の真空容器Σを置ビ提供する。In order to achieve the above object (2. In the present invention, a ring-shaped Nitrogen container is provided with a divided part extending 11Y1 gap in the circumferential direction and integrally fastened with an insulator interposed in this part 4i'1 part. , a bellows that seals the inner +q side of the upper slurry portion λ, and a protection plate that covers the P1 circumference of the vacuum vessel and the bellows and blocks radiant heat from the plasma. , in which a support ring of a plurality of annular plates is interposed in the divided portion, and the portion of the protective plate facing the corresponding portions 14..11.9 is axially 1' : #
'il 1 minute and set up the self-bows, these retainer plate pieces are largely fixed to the support ring, and the said bellows are attached to each retainer 1. A vacuum vessel Σ for a υ fusion device is provided, characterized in that it is constructed by filling a ψ plate piece.

〔発明の実加ｊし′］ｌ〕[Actual addition of the invention]

以Ｆ本発１！／Ｊの一失ｈｊｔｊ　ｉ４ｉ、ｌを・図面
によって説明する。First F main departure 1! /J's loss hjtj i4i,l will be explained using drawings.

第４図において、ペロー゛ズ（′２）はｌピッチ毎に支
持リング（う１にｆ火炎する。支持リング（５）は、真
空容器（１）の内（１１１ｉへ延長され、先端部には軸
方向に分割されたベローズ保護板・６）が保護板取付ボ
ルト（７）によって固定される。夫々のベローズ保護板
１６）は、プラズマからの輻射熱がベローズ（２）へ届
くことのないように隣接する保護板を重ね合わて配役さ
れる。In Fig. 4, the perose ('2) flames the support ring (11) every l pitch.The support ring (5) is extended into the vacuum vessel (1) (111i) and the tip is A bellows protection plate 6) divided in the axial direction is fixed by a protection plate mounting bolt (7).Each bellows protection plate 16) is designed to prevent radiant heat from the plasma from reaching the bellows (2). The protection plate adjacent to the plate is placed on top of the other.

支持リング（５）は、真空容器ｆｉ＋の外側へも延長し
、その間に絶縁物（３）をはさんで、ｋ・付ボルト（８
）によりＪＡ空容器（１）のフランジ（１ａ）に固定す
る。真空容器＋１＋のフランジ（１ａ）は締付ボルト（
８）の周りｒｊとフランジ（１ａ）との恢触部には絶縁
物ｔｌＧ＋が入れである。また、支持リング（５）の外
側には加熱・冷却用の管Ｕが固着されている。The support ring (5) also extends to the outside of the vacuum vessel fi+, and the insulator (3) is sandwiched between them.
) to the flange (1a) of the JA empty container (1). The flange (1a) of the vacuum vessel +1+ is attached to the tightening bolt (
8) An insulator tlG+ is inserted around the contact portion between rj and the flange (1a). Further, a heating/cooling tube U is fixed to the outside of the support ring (5).

次にこの実ｊＭ　ＶＩＪの作用について説明する。Next, the action of this real jM VIJ will be explained.

ます、ベローズ（２）に働く電磁力については、ベロー
ズ（２）の支持固定部が１ピツチ毎に設けられており、
従来例のような数ピツチ毎（二設ける場合に比べて、支
持固定部１カ所当たりの荷車は大幅に軽減される。一般
にベローズに発生する応力の中で厳しいのは、支持固定
のための溶接部であって、この蘭所の荷重が軽減されて
応力値が小さくなることは、ベローズの信頼性同上に大
きく寄与する、また、ベローズ保護板＜Ｇｌは、軸方向
に細分化されており、プラズマ異常消減時等に保護板（
６）に流れる渦竜流は小さくなり、生ずる電磁力も軽部
される。また保〃板（６）はプラズマから多大なＩＩ＋
８８１・ｊ熱を受けるが、細分化してそれぞれの保護板
（６）に−）いてＪ４章容器（１）の外側に％ｊ（ｉ］
）を設けて冷却しているので、保護板（６）に対する冷
却効果が大きくなり、温良上昇を低く抑えることができ
る。保護板（６）の温度が低く、細分化しであることは
、熱応力の軽い−にもなり、保４Ｗ板（（５）の杓科の
裕度か大きくなって、真望合器のイ、：頼性がｌｉＪ上
する。Regarding the electromagnetic force acting on the bellows (2), a support and fixing part of the bellows (2) is provided at each pitch.
Compared to the conventional case where two pitches are provided, the load per supporting and fixing part is significantly reduced.Generally, the severest stress that occurs in bellows is the welding for supporting and fixing. The reduction in the stress value due to the reduction of the load on the orchid greatly contributes to the reliability of the bellows, and the bellows protection plate <Gl is subdivided in the axial direction, Protective plate (
6) The whirlpool current flowing in the area becomes smaller and the resulting electromagnetic force is also reduced. Also, the protection plate (6) is protected from plasma by a large amount of II+.
881・j It receives heat, but it is subdivided into each protective plate (6) -) and %j (i) is placed on the outside of the J4 container (1).
) is provided for cooling, the cooling effect on the protection plate (6) is increased, and the rise in temperature can be suppressed to a low level. The fact that the temperature of the protection plate (6) is low and that it is segmented also results in light thermal stress, and the ladle tolerance of the protection plate (5) increases, making it possible to improve the ,: Reliability increases by liJ.

さら（二、真を谷箸ｂ（１）のベーキングの図）（二は
、ベローズ文トｊリング（５）の管Ｕυに尚、福流体を
流１ことにより、ベローズ（２）の熱伝導の長さは１ピ
ツチのみとなって、従来例に比べて加熱時間が短かくな
ると同時に、ベローズ内の温度差が小さくなり、熱Ｉ心
力が軽減されてベローズの強度が向上する。In addition, (2) Diagram of baking of Tani chopsticks b (1) (2) By flowing liquid into the tube Uυ of bellows ring (5), heat conduction of bellows (2) is achieved. The length of the bellows is only one pitch, so the heating time is shortened compared to the conventional example, and at the same time, the temperature difference within the bellows is reduced, the thermal I core force is reduced, and the strength of the bellows is improved.

以上、本実旌１ダｊでは成形ベローズ（二ついて説明シ
タが、ｔｄ　接ベローズに適用することもｂ」能である
。As mentioned above, in this practical example, two molded bellows are used in the explanation, but it can also be applied to td-contact bellows.

〔発明の効果〕〔Effect of the invention〕

思ｈ　１ｉ−１述したように本発明によれはベローズの
強を見が向上し、ベローズ保護板の冷却性能及び、強度
も向上し、ベーキング時のベローズの熱応力が１−１　
ｋできる等の効果がある。As mentioned above, according to the present invention, the strength of the bellows is improved, the cooling performance and strength of the bellows protection plate are also improved, and the thermal stress of the bellows during baking is reduced by 1-1.
There are effects such as being able to do k.

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

第１図および第２因はそれぞれ従来の核融合装置の真空
容器製置を示す一部欠戯平面図、第３区１は第２図の要
笥５の横断面図、第４図は本発明の一芙施β゛りを示す
核融８表置の真空容器装置である。−（１）・・・真苗
容器　　　　　（１ａ）・・・内同体（２）・・・へｏ
　−ス（３）・・・糸已縁物（５）・・−交付リング　
　　　（６）・・・保様板（８）・・縄付ポル）　　　
　　Ｉ！０）・・・絶縁物Ｕυ・・・冷却管、 代理人　弁即士　則　近　恵　佑 （ほか１名）Figures 1 and 2 are partially cut-out plan views showing the construction of a vacuum vessel in a conventional nuclear fusion device, Section 3 is a cross-sectional view of the main compartment 5 in Figure 2, and Figure 4 is a main This is a vacuum vessel device for nuclear fusion 8 placed on top, showing one aspect of the invention. -(1)...Manae container (1a)...Internal body (2)...to o
-S (3)...Threaded edge (5)...-Issuance ring
(6)...Hosama board (8)...Poru with rope)
I! 0)...Insulator Uυ...Cooling pipe, Agent: Yu Chika, attorney, Noriyuki Chika (and 1 other person)

Claims (2)

【特許請求の範囲】[Claims] （１）　　周方間に間隙を右下る分割部を設けこの分割
Ｈｊ’　ｉ：Ｘ’６　は物を介在させて一体的に締結し
た円環状の真草容器と、上記分？ｆ：ｊ都の内周側をシ
ールするベローズと、これら真ｑ容器とベローズとの内
周面を覆いプラズマからの輻射熱を阻止する保護板とを
備えた核鴨台云ｉ白、の真空容器装置に３いて、目り泥
分が１部にネジ数置の環状板の支持リングを重ねて介装
し、保護板の該分＾り邪に対向する部位を輔力回に細分
して配設し、これらの保護板片を大々上記支持リングに
固定するとともに前記ベローズを夫々の保護板片に固有
して構成したことを特徴と゛する核融合装置の輿望容器
装置。(1) A dividing part is provided in the circumferential direction with a gap extending downward to the right, and this division Hj' i: f: A vacuum vessel of nuclear power plant, which is equipped with a bellows that seals the inner circumferential side of the cell, and a protective plate that covers the inner circumferential surfaces of the vacuum vessel and the bellows and blocks radiant heat from the plasma. In the device, a support ring of an annular plate with several screws is placed on one part of the device, and the part of the protective plate facing the warp is subdivided into support rings. A viewing container device for a nuclear fusion device, characterized in that these protective plate pieces are largely fixed to the support ring, and the bellows are configured to be unique to each of the protective plate pieces. （２）　　支持リングに流体通路を設けたことを特徴と
する特計１石求の範囲す、１項記ルｙの核融合装置の真
空容器装置。(2) A vacuum vessel device for a nuclear fusion device according to item 1, characterized in that a fluid passage is provided in the support ring.
JP58043118A 1983-03-17 1983-03-17 Vacuum vessel device of nuclear fusion device Pending JPS59170787A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58043118A JPS59170787A (en) 1983-03-17 1983-03-17 Vacuum vessel device of nuclear fusion device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58043118A JPS59170787A (en) 1983-03-17 1983-03-17 Vacuum vessel device of nuclear fusion device

Publications (1)

Publication Number Publication Date
JPS59170787A true JPS59170787A (en) 1984-09-27

Family

ID=12654919

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58043118A Pending JPS59170787A (en) 1983-03-17 1983-03-17 Vacuum vessel device of nuclear fusion device

Country Status (1)

Country Link
JP (1) JPS59170787A (en)

Similar Documents

Publication Publication Date Title
US4649018A (en) Container for the storage of radioactive elements
US3424239A (en) Nuclear reactor pressure vessel
US11688523B2 (en) System for confining and cooling melt from the core of a water-moderated nuclear reactor
US20230005629A1 (en) System for confining and cooling melt from the core of a nuclear reactor
US4289582A (en) Nuclear reactor collecting tank with thermal insulation
RU2084975C1 (en) Container for spent fuel transporting and/or storage
JPH02105095A (en) Heat-insulating shielding body
US2849387A (en) Corrosion resistant jacketed metal body
US3794559A (en) Pressure vessels
US3293139A (en) Prestressed concrete pressure vessel for nuclear reactors
US4284474A (en) Structures for heat insulation of surfaces within a nuclear reactor
JPS59170787A (en) Vacuum vessel device of nuclear fusion device
US4433722A (en) Heat exchanger having pipe coils supported in support plates
JPH0226078Y2 (en)
US4349991A (en) Closing device for large passages in a prestressed pressure vessel
US4016035A (en) Fuel assembly support column for a nuclear reactor diagrid
US20230268087A1 (en) System for confining and cooling melt from the core of a nuclear reactor
CA3191248A1 (en) Corium localizing and cooling system of a nuclear reactor
US5544210A (en) Pressure vessel apparatus for containing fluid under high temperature and pressure
US3678920A (en) Radioisotope heat source boiler for power generators
US4666652A (en) Fast neutron nuclear reactor comprising a suspended sealing slab and main vessel
US4569508A (en) Metallurgical vessel having an opening and a flange around the opening
US3863410A (en) Pressure-tight reactor tank
JP7494384B2 (en) System for localization and cooling of molten core in nuclear reactors
JP7506825B2 (en) System for localization and cooling of molten core in nuclear reactors