JPH0315795A - Nuclear fusion blanket - Google Patents
Nuclear fusion blanketInfo
- Publication number
- JPH0315795A JPH0315795A JP1149325A JP14932589A JPH0315795A JP H0315795 A JPH0315795 A JP H0315795A JP 1149325 A JP1149325 A JP 1149325A JP 14932589 A JP14932589 A JP 14932589A JP H0315795 A JPH0315795 A JP H0315795A
- Authority
- JP
- Japan
- Prior art keywords
- temp
- bleeder
- control layer
- blanket
- 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
- 230000004927 fusion Effects 0.000 title claims abstract description 12
- 239000000835 fiber Substances 0.000 claims abstract description 31
- 239000000919 ceramic Substances 0.000 claims abstract description 27
- 238000001816 cooling Methods 0.000 claims abstract description 17
- 239000000463 material Substances 0.000 claims abstract description 15
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 claims abstract description 12
- 229910052722 tritium Inorganic materials 0.000 claims abstract description 12
- 239000007789 gas Substances 0.000 claims description 13
- 239000001307 helium Substances 0.000 claims description 8
- 229910052734 helium Inorganic materials 0.000 claims description 8
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims description 8
- 239000007787 solid Substances 0.000 claims description 7
- 239000012530 fluid Substances 0.000 claims description 2
- 230000005855 radiation Effects 0.000 abstract description 7
- 238000005192 partition Methods 0.000 abstract description 6
- 230000010355 oscillation Effects 0.000 abstract 2
- 238000000034 method Methods 0.000 description 13
- 235000021307 Triticum Nutrition 0.000 description 4
- 241000209140 Triticum Species 0.000 description 4
- 239000006091 Macor Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 230000008961 swelling Effects 0.000 description 3
- 238000009423 ventilation Methods 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 description 2
- 229910052581 Si3N4 Inorganic materials 0.000 description 2
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 2
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 229910052744 lithium Inorganic materials 0.000 description 2
- FUJCRWPEOMXPAD-UHFFFAOYSA-N lithium oxide Chemical compound [Li+].[Li+].[O-2] FUJCRWPEOMXPAD-UHFFFAOYSA-N 0.000 description 2
- HQVNEWCFYHHQES-UHFFFAOYSA-N silicon nitride Chemical compound N12[Si]34N5[Si]62N3[Si]51N64 HQVNEWCFYHHQES-UHFFFAOYSA-N 0.000 description 2
- 125000006850 spacer group Chemical group 0.000 description 2
- 241000208140 Acer Species 0.000 description 1
- 229920000049 Carbon (fiber) Polymers 0.000 description 1
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
- 101100264174 Mus musculus Xiap gene Proteins 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- 239000004917 carbon fiber Substances 0.000 description 1
- 229910010293 ceramic material Inorganic materials 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000008187 granular material Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 229910001947 lithium oxide Inorganic materials 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical compound C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 239000000377 silicon dioxide Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- Physical Or Chemical Processes And Apparatus (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は固体トリチウム・ブリーダを使用する核融合炉
の温度制御層におけるブランケットに関する。DETAILED DESCRIPTION OF THE INVENTION Field of the Invention The present invention relates to blankets in the temperature control layer of fusion reactors using solid tritium bleeders.
核融合炉におけるブランケットは、核融合プラズマを包
むように置かれ、
Ｈ）核融合エネルギー（重水素・トリチウムを燃料とす
る炉では、中性子が持ち出るエネルギー２Ｄ＋ ”Ｔ−
＋ ’Ｈｅ（３．５ＭｅＶ） ＋ｎ （１４．１ＭｅＶ
） ）を熱エネルイーに変換する．
（ロ）トリチクムを再生産する（ ’Ｌｉ ＋ ｎ →
’Ｈａ（ ２．１Ｍｏｎ） ＋ ”Ｔ（２．７ＭｅＶ）
）．←→ 外部への放射線漏れを防ぐ放射線遮蔽体と
なる．
等の機能を有する。In a fusion reactor, a blanket is placed to enclose the fusion plasma, and H) Fusion energy (in reactors fueled by deuterium and tritium, the energy carried out by neutrons is 2D+ "T-").
+ 'He (3.5MeV) +n (14.1MeV
) ) into thermal energy E. (b) Reproduce triticum ('Li + n →
'Ha(2.1Mon) + "T(2.7MeV)
). ←→ Acts as a radiation shield to prevent radiation leakage to the outside. It has the following functions.
トリチウム・ブリーダ（Ｌｔ２０． ＬｔＡＩＯ２等）
は、その特性上，約４００〜１０００℃に温度制御され
る必要があシ，ブリーダと冷却管又は構造材との間に温
度創御層が設けられる．
温度制御層の従来技術としては，第４図乃至第６図に示
すよ５κ，マプール（ガ２スに似た固体）で中間層を形
成する方式，或はヘリウムガスイヤツプを利用する方式
（例えば特公昭６２−５７２３５号公報）等が提案され
ている．
第４図乃至第６図において、１はブリーダ，２は冷却管
，３はシェル（ＩＩ，構造材），５ａはマコール，
５ｂはヘリウムガスギャップ， ５ｃはスペーサである
。Tritium breeder (Lt20. LtAIO2 etc.)
Due to its characteristics, it is necessary to control the temperature to approximately 400 to 1000°C, and a temperature control layer is provided between the bleeder and the cooling pipe or structural material. As shown in Figures 4 to 6, conventional techniques for the temperature control layer include a method of forming an intermediate layer with 5κ, maple (a solid similar to gas), or a method of using a helium gas earpipe. (For example, Japanese Patent Publication No. 62-57235) etc. have been proposed. In FIGS. 4 to 6, 1 is a bleeder, 2 is a cooling pipe, 3 is a shell (II, structural material), 5a is a macor,
5b is a helium gas gap, and 5c is a spacer.
第６図（ａ）は温度制御層としてマコール５ａを使用し
た例で、第６図（ｂ） ， （Ｃ） ， （ｄ）はそれ
ぞれヘリウムガスギャップ方式を示している．
〔発明が解決しようとする課題〕
前述のような従来技術には下記の問題点があう、ブラン
ケットとしての実用性を欠く恐れが大きい。Figure 6(a) shows an example in which Macor 5a is used as the temperature control layer, and Figures 6(b), (C), and (d) each show the helium gas gap method. [Problems to be Solved by the Invention] The prior art as described above has the following problems, and there is a great possibility that it will lack practicality as a blanket.
（１）マコールの場合：
脆く、割れる可能性がある．
クッション性がない．ブリーダの種類によっては、使用
中にスエリング（膨張する）を起すものかあシ、クッシ
ョン性がないと，スエリング，熱膨張等の寸法変化，機
械的振動に対する考慮が必要となる。(1) In the case of Makor: It is brittle and may break. There is no cushioning. Depending on the type of bleeder, it may swell during use, and if it does not have cushioning properties, consideration must be given to swelling, dimensional changes such as thermal expansion, and mechanical vibration.
（２）ヘリウムかスギャツプ方式の場合：冷却管とゾリ
ーダ間に適当なスペーサを入れる等の工夫がいる。(2) In the case of helium or gap type: It is necessary to take measures such as inserting an appropriate spacer between the cooling pipe and the zorider.
冷却管外表面温度は、約３００℃（実験用＝１００〜３
００℃），ブリーダは約４００〜１０００℃と高温でか
つ，温度差が大きい。高放射線（中性子等）を受けるの
で、スイーサの構造・材質に対する制約が大きい．また
大きな据付空間を必要とする．
なお，上記の温度は、Ｌｒ２０ （酸化リチウム）ブリ
ーダを高圧水で冷却する場合の例である。The outer surface temperature of the cooling tube is approximately 300℃ (experimental use = 100~3
00°C), the bleeder is at a high temperature of approximately 400 to 1000°C, and there is a large temperature difference. Since it is exposed to high radiation (neutrons, etc.), there are significant restrictions on the structure and material of the sweeter. It also requires a large installation space. Note that the above temperature is an example when the Lr20 (lithium oxide) bleeder is cooled with high-pressure water.
温度制御層として、下配の特性を有するセラミックス・
７アイパを採用する．
（１）クッション性がある。（もろくない。寸法変化追
従性大）
（２）ブリーダと構造材・冷却管との間の熱抵抗値の調
整が容易。As a temperature control layer, ceramics with the characteristics of the lower layer
Adopts 7 AIPA. (1) Has cushioning properties. (Not brittle. Great ability to follow dimensional changes) (2) Easy adjustment of thermal resistance between the bleeder and structural material/cooling pipe.
（３）ブリーダ等他の接触材料と両立性のあるセラ實ツ
クス（アルξナ，窒化ケイ素等）を選択できるので、選
択範囲が拡大する。(3) Since it is possible to select a ceramic material (aluminum, silicon nitride, etc.) that is compatible with other contact materials such as a bleeder, the range of selection is expanded.
（４）温度制御層用のスペースが小でよい。(4) Only a small space is required for the temperature control layer.
以上によシブランケットの実現可能性が大となる。This increases the possibility of realizing the Yoshiblanket.
なお，セラミックス・ファイバの例としては、アルミナ
ファイバ，シリカ７アイパ，ダラスファイバ，カーボン
ファイバ等がある．ファイバの寸法形状としては、種々
考えられるが、例えば，直径０．１〜２■，長さ２０〜
７０ ｍ．，直径断面形状：円，多角形等。Examples of ceramic fibers include alumina fiber, silica 7-iper, Dallas fiber, and carbon fiber. Various dimensions and shapes of the fiber can be considered, but for example, a diameter of 0.1 to 2 cm and a length of 20 to 2 cm.
70 m. , Diameter cross-sectional shape: circle, polygon, etc.
ブリーダ内では，種々の熱が発生する。（主要な発生熱
としては，ブリーダ内に飛び込んだ中性子やガンマ線の
運動エネルイが熱エネルイκ変化することによる熱，中
性子がゾリーダ構戒要素であるＬ１（リチウム）と、核
反応を起こし，トリチクムを生成する際に発生する熱が
ある．）これらの熱の単位時間当シの発生割合は，必ず
しも一定ではなく、種々の条件によう変動する．冷却管
中を流れる冷却水の流速，温度，圧力等の条件もある程
度の範囲内で変更することもあ）５る。このように変動
する条件の下で、ブリーダの温度は、その特性上、約４
００〜１０００℃（ Ｌ１，０ゾリーダの例）Ｋ制御さ
れる必要がある．固体ブリーダは−体物（モノリシツク
）の場合もあれば、粒状（この場合は、ブリーダ粒は薄
い金属板で包む等の工夫をして使用する。）の場合等、
種々考えられるが，いずれにしても固体であシ、スエリ
ング（中性子，ガンマ線等の放射線によシふくらむこと
を言ウ．），熱膨張等の寸法変化，各種の原因によシ発
生する振動に対する配慮が必要である。又，使用される
環境も高温（ Ｌｉ２０ブリーダの場合， 約３００〜
１０００℃），高放射線下と苛酷である。Various kinds of heat are generated inside the bleeder. (The main heat generated is the heat caused by the kinetic energy of neutrons and gamma rays that entered the bleeder changing into thermal energy κ, and the neutrons causing a nuclear reaction with L1 (lithium), which is a component of Zorida, and causing triticum. (There is heat generated during generation.) The rate of generation of these heat per unit time is not necessarily constant and varies depending on various conditions. Conditions such as the flow rate, temperature, and pressure of the cooling water flowing through the cooling pipes may also be changed within a certain range). Under these fluctuating conditions, the temperature of the bleeder is, by its nature, approximately 4
00 to 1000℃ (example of L1,0 Zorida) K must be controlled. Solid bleeders may be monolithic, or granular (in this case, the bleeder granules are wrapped in a thin metal plate, etc.).
There are various possibilities, but in any case, it is a solid, and it is against swelling (swelling due to radiation such as neutrons and gamma rays), dimensional changes such as thermal expansion, and vibrations caused by various causes. Consideration is required. Also, the environment in which it is used is high temperature (approximately 300~300℃ for Li20 bleeder)
(1000℃), high radiation and harsh conditions.
このよう欧悪条件下において、適度な熱伝達率ヲ持つ、
セラミックス・ファイバは、優れた機能を有する．
即ち、セラミックス・ファイバは、寸法変化や振動に対
してはクッションとなう、高温に対しては、余裕のある
耐高温特性を有し、高放射線に対しても高い安定度を有
する。また，ブリーダや、構造材等、接触して使用され
る材料に対して良好な両立性を有し、所要スペースもそ
れほど大きくない。さらに、このセラミックス・７アイ
パに適切な流体を（例えば、ヘリウム・ガス）適量流す
ことによシ、その熱伝達率を調整可能であシ、条件追随
性が良い。Under such adverse conditions, it has an appropriate heat transfer rate.
Ceramic fibers have excellent functionality. That is, ceramic fibers provide a cushion against dimensional changes and vibrations, have sufficient high-temperature resistance characteristics, and have high stability against high radiation. In addition, it has good compatibility with materials used in contact with it, such as bleeders and structural materials, and does not require much space. Furthermore, by flowing an appropriate amount of an appropriate fluid (for example, helium gas) through this ceramic 7-IPA, the heat transfer coefficient can be adjusted, and the condition can be easily followed.
第１図乃至第３図において，１はトリチウム・ブリーダ
，２は冷却管，３はシェル（！！，構造材），４は仕切
板，５は温度制御層，６はセラミックス・ファイバ，７
は板，８は線材，９は通気用大である．
核融合炉のブランケットは、核融合エネルイを熱エネル
イに変換・回収する、またトリチクムを生産・回収する
等重要な機能を有している．トリチウム・ブリーダとし
ては、液体金属，固体等が使用される．固体ブリーダ方
式の場合，ブリーダを詰めたシェルの中に除熱・温度制
御・エネルギ回収用の冷却管を通すブリーダ・アウトサ
イド・チューブ（ ＢＯＴ ： Ｂｒｅｅｄｅｒ Ｏｕ
ｔｓｉｄｅ Ｔｕｂｅ ）方式や、ブリーダ・イン・チ
ューブ（ＢＩＴ）方式等が考えられるが，ここでは、Ｂ
ＯＴ方式の実施例について説明する。In Figures 1 to 3, 1 is a tritium bleeder, 2 is a cooling pipe, 3 is a shell (!!, structural material), 4 is a partition plate, 5 is a temperature control layer, 6 is a ceramic fiber, 7
is a plate, 8 is a wire rod, and 9 is a large one for ventilation. The blanket of a fusion reactor has important functions such as converting and recovering fusion energy into thermal energy, and producing and recovering triticum. Liquid metals, solids, etc. are used as tritium breeders. In the case of the solid bleeder method, a bleeder outside tube (BOT) is used to pass cooling pipes for heat removal, temperature control, and energy recovery into the shell filled with the bleeder.
Possible methods include the tside tube) method and the bleeder-in-tube (BIT) method, but here we will use the BIT method.
An example of the OT method will be described.
トリチクム・ブリーダ（ Ｌ１２０， Ｌｉ＃Ｏ，等）
１は、その特性上、約４００〜１，０００ ′ｃに温度
制御される必要があシ、冷却管２の温度は約３００℃が
、又シエル（壁，構造材）３や、仕切板４等は約３００
℃以下に保持されることが適当とされている。Triticum breeda (L120, Li#O, etc.)
1, due to its characteristics, needs to be temperature controlled to about 400 to 1,000'C, and the temperature of the cooling pipe 2 is about 300C, but also the shell (wall, structural material) 3 and the partition plate 4. etc. is about 300
It is considered appropriate to maintain the temperature below ℃.
そこで、ブリーダ１と冷却管２又はシエル３，や仕切板
４との間には、温度制御層５が設置される．本発明では
，この温度制御層５として、セラミックス・７アイパ６
を使用する．
第２図（ｂ），第３図（ｂ）は、第２図（ａ），第３図
（ｍｌに使用したセラぢツクス・ファイバ６単体の拡大
図であシ、もちろん，これら以外の形状のファイバ、或
は各形状寸法のミックス（混合）使用も可能である．
セラミックス・ファイバのセッティング（組み合せ加工
）は次のようにして行う。Therefore, a temperature control layer 5 is installed between the bleeder 1 and the cooling pipe 2 or the shell 3 or the partition plate 4. In the present invention, the temperature control layer 5 is made of ceramic 7-iper 6.
Use. Figures 2(b) and 3(b) are enlarged views of the single ceramic fiber 6 used in Figures 2(a) and 3 (ml). It is also possible to use a mix of fibers or different shapes and sizes.Setting (combining) ceramic fibers is done as follows.
セラミックス・ファイバ６は、各単体をただ置いただけ
では、バラバラと散逸してしまうため、第２図（ａ），
第３図（ａ）に示す如く、板７と線材８によシセッティ
ング（組み合せ加工）しておくことが適当である．
セッティングの仕方としては，例えば、まず板７を作業
床（図示していない）上に置き、該板７上にセラミック
・ファイバ６を１〜２層仮置きし，点又は線溶接によう
，セラミックス・ファイバ同志及びセラミックス・ファ
イバと板７とを適度に結合させる。次に再度、セラミッ
クス・ファイバを２〜３層仮置きし、点又は線溶接によ
う，セラミックス・ファイバ同志を適度に結合させる．
これを所要回数行ない，最後に、板８を置き、点又は線
溶接によ１線材８とセラミックス・ファイバ６とを適度
に結合させる。If the ceramic fiber 6 is simply placed on its own, it will dissipate in pieces;
As shown in FIG. 3(a), it is appropriate to set (combine) the plate 7 and wire 8. The setting method is, for example, to first place the plate 7 on a work floor (not shown), temporarily place one or two layers of ceramic fiber 6 on the plate 7, and place the ceramic fiber 6 on the plate 7 for spot or line welding. - Properly bond the fibers and the ceramic fibers to the plate 7. Next, temporarily place two to three layers of ceramic fibers again, and bond the ceramic fibers appropriately by point or line welding.
This is repeated a required number of times, and finally, the plate 8 is placed and the wire rod 8 and the ceramic fiber 6 are properly bonded by spot or line welding.
尚、板７には通気用穴９が設けてある．通気用穴９には
、温度制御用の気体（例：Ｈｅガス），及びトリチウム
・スウイープ用の気体σリチウムを取シ出すことを目的
としたガスを言う）（例：Ｈｅガス）が通る。また板７
は、短冊（たんざく）状の多数枚の板の組み合せとする
、又はリプを設ける、或はプレスによう（補強）溝を設
ける等の変更を加えることもできる。Note that the plate 7 is provided with ventilation holes 9. A gas for temperature control (eg, He gas) and a gas for extracting the gas σ lithium for tritium sweep (eg, He gas) pass through the ventilation holes 9. Also board 7
It is also possible to make changes such as combining a large number of strip-shaped plates, providing a lip, or providing a reinforcing groove in the press.
セラミックス・ファイバをシェルに設置する方法は次の
通シである。The method for installing the ceramic fiber in the shell is as follows.
板状にセッティングしたセラミックス・ファイバを、さ
らに箱状に組み合わせ、その中に、トリチウム・ブリー
ダ１を収容した後、シエル３に設置する方法、又は板状
にセッティングしたセラミックス・ファイバをまず、シ
エ／Ｉ／３に設置後、トリチウム・ブリーダ１を収容す
る方法等がある。Ceramic fibers set in a plate shape are further combined into a box shape, and the tritium bleeder 1 is housed in the box, and then installed in the shell 3, or the ceramic fibers set in a plate shape are first placed in the shell 3. There are methods of accommodating the tritium breeder 1 after installing it in I/3.
本発明ではブランケットの温度制御層として、セラミッ
クス・ファイバを採用しているため、次記の如き効果が
ある。In the present invention, since ceramic fiber is employed as the temperature control layer of the blanket, the following effects are achieved.
（１）冷却管とブリーダ関に、寸法変化追従性が大きい
ファイバ層があるため，クッション性が大きい．
（２）ブリーダ等他の接触材料と両立性のある材（アル
ミナ，窒化ケイ素等）を選択できる。(1) There is a fiber layer between the cooling pipe and the bleeder that has a high ability to follow dimensional changes, so it has great cushioning properties. (2) Materials (alumina, silicon nitride, etc.) that are compatible with other contact materials such as bleeders can be selected.
（３）温度制御層用のスイースが小さくてよい。(3) The swiss for the temperature control layer may be small.
（４） ブリーダ温度制御層にヘリウムガスを流す時
は、ブリーダと構造材・冷却管との間の熱抵抗値の調整
が容昌であシ、ブランケットとしての実用性が高くなる
．(4) When helium gas is flowed through the bleeder temperature control layer, the thermal resistance value between the bleeder and the structural material/cooling pipe can be easily adjusted, making it more practical as a blanket.
第ｌ図は本発明の実施例の縦断面図、第２図（ａ）は第
ｌ図Ａ部の拡大図、第２図（ｂ）は第２図（ａＪκおけ
るセラミックス・ファイバ単体の外観図、第３図（ａ）
は他の実施例における第ｌ図Ａ部の拡大図，第３図（ｂ
）は第３図（ａ）におけるセラミックス・ファイバ単体
の外観図、第４図は従来のブランケットの概要図、第５
図は第４図Ｂ部の拡大図、第６図（ａ）はマコールを使
用した従来装置の要部拡大図、第６図（ｂ）はヘリウム
ガスギャップ方式の従来装置の要部拡大図、第６図（Ｃ
）は第６図（ｂ）の断面図、第６図（ｄ）は第４図のシ
ェル部分の拡大図である．ｌ・・・トリチウム・ブリー
ダ， ２・・・冷却管，３・・・シェル（構造材），
４・・・仕切板，５・・・温度制御層， ６・・・
セラミックス・ファイバ。Figure 1 is a vertical sectional view of an embodiment of the present invention, Figure 2 (a) is an enlarged view of section A in Figure 1, and Figure 2 (b) is an external view of a single ceramic fiber in Figure 2 (aJκ). , Figure 3(a)
is an enlarged view of part A in FIG. 1 in another embodiment, and FIG.
) is an external view of the single ceramic fiber in Figure 3(a), Figure 4 is a schematic diagram of the conventional blanket, and Figure 5 is a schematic diagram of the conventional blanket.
The figure is an enlarged view of part B in Fig. 4, Fig. 6 (a) is an enlarged view of the main part of a conventional device using Macor, and Fig. 6 (b) is an enlarged view of the main part of a conventional device using a helium gas gap method. Figure 6 (C
) is a sectional view of FIG. 6(b), and FIG. 6(d) is an enlarged view of the shell portion of FIG. 4. 1... Tritium bleeder, 2... Cooling pipe, 3... Shell (structural material),
4... Partition plate, 5... Temperature control layer, 6...
Ceramic fiber.
Claims (2)
ンケットにおいて、ブリーダと冷却管又はブランケット
壁等の構造材との間に存在するブリーダ温度制御層とし
てセラミックス・ファイバの層を設けたことを特徴とす
る核融合ブランケツト。(1) A nuclear fusion blanket using a solid tritium bleeder, characterized in that a ceramic fiber layer is provided as a bleeder temperature control layer between the bleeder and a structural material such as a cooling pipe or blanket wall. Fusion blanket.
流体を流し、ブリーダ温度制御層の熱伝導率を制御可能
に構成した請求項（１）記載の核融合ブランケット。(2) The nuclear fusion blanket according to claim (1), wherein the thermal conductivity of the bleeder temperature control layer can be controlled by flowing a fluid such as helium gas through the ceramic fiber layer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1149325A JPH0315795A (en) | 1989-06-14 | 1989-06-14 | Nuclear fusion blanket |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1149325A JPH0315795A (en) | 1989-06-14 | 1989-06-14 | Nuclear fusion blanket |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0315795A true JPH0315795A (en) | 1991-01-24 |
Family
ID=15472647
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1149325A Pending JPH0315795A (en) | 1989-06-14 | 1989-06-14 | Nuclear fusion blanket |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0315795A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5248843A (en) * | 1991-02-08 | 1993-09-28 | Sight & Sound Incorporated | Electronic musical instrument with sound-control panel and keyboard |
-
1989
- 1989-06-14 JP JP1149325A patent/JPH0315795A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5248843A (en) * | 1991-02-08 | 1993-09-28 | Sight & Sound Incorporated | Electronic musical instrument with sound-control panel and keyboard |
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