JPH0246919B2 - - Google Patents
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- Publication number
- JPH0246919B2 JPH0246919B2 JP59013058A JP1305884A JPH0246919B2 JP H0246919 B2 JPH0246919 B2 JP H0246919B2 JP 59013058 A JP59013058 A JP 59013058A JP 1305884 A JP1305884 A JP 1305884A JP H0246919 B2 JPH0246919 B2 JP H0246919B2
- Authority
- JP
- Japan
- Prior art keywords
- coolant
- wall
- manifold
- blanket
- flow path
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
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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
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- Plasma Technology (AREA)
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、核融合炉用ブランケツトのプラズマ
対向面を構成する第1壁の冷却構造の改良に関す
るものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to an improvement in the cooling structure of a first wall forming a plasma facing surface of a blanket for a nuclear fusion reactor.
〔従来の技術〕 トカマク型核融合炉の概略を説明する。[Conventional technology] An overview of a tokamak-type fusion reactor will be explained.
トカマク型核融合炉は、円周方向に沿つて作つ
たプラズマ中に電流を流して、この電流によつて
発生する磁場の力でプラズマを閉じ込めるもの
で、第1図に示す如くプラズマ1を囲むように内
側ブランケツト2、外側ブランケツト2′、内側
遮蔽体3、外側遮蔽体3′、トロイダル磁場コイ
ル4、ポロイダル磁場コイル5、ダイバータ6、
排気装置7等が配置されている。 A tokamak-type fusion reactor is one in which a current is passed through the plasma created along the circumference, and the plasma is confined by the force of the magnetic field generated by this current, which surrounds the plasma 1 as shown in Figure 1. Inner blanket 2, outer blanket 2', inner shield 3, outer shield 3', toroidal magnetic field coil 4, poloidal magnetic field coil 5, diverter 6,
An exhaust device 7 and the like are arranged.
トカマク型核融合炉は概ね上記のような機器で
構成されているが、これらの中で内側、外側ブラ
ンケツト2,2′は、容器内で核融合反応によつ
て発生した中性子のもつ核エネルギーを熱エネル
ギーに変換する機能、該中性子と容器内の酸化リ
チウムとが反応して核融合炉の燃料となるトリチ
ウム(三重水素)を生産する機能、遮蔽体と共に
中性子を遮蔽する機能を備えており、核融合炉の
重要な機器の一つである。第1壁はこの内側、外
側ブランケツト2,2′のプラズマ1の対向面と
なる構造物で、直接プラズマ1からの大きな熱負
荷、粒子負荷を受ける厳しい条件下にあるため、
十分な冷却性能を有することが要求される。 A tokamak-type fusion reactor is generally composed of the equipment described above, and among these, the inner and outer blankets 2 and 2' are used to absorb the nuclear energy of neutrons generated by the fusion reaction inside the container. It has the following functions: converting the neutrons into thermal energy, producing tritium (tritium), which is the fuel for the fusion reactor by reacting the neutrons with lithium oxide in the container, and shielding the neutrons with a shield. It is one of the important pieces of equipment in a nuclear fusion reactor. The first wall is a structure that faces the plasma 1 of the inner and outer blankets 2, 2', and is under severe conditions where it is directly subjected to a large heat load and particle load from the plasma 1.
It is required to have sufficient cooling performance.
ところで、トカマク型核融合炉の第1壁8は、
従来第2図に示すごとく、冷却材をポロイダル方
向即ち矢印Aの方向に流す方式を採用し冷却して
いるが、その形状がトーラス状をなしているた
め、冷却材流路のピツチが流れ方向で変化すると
言う問題が生じる。即ち、最も厳しい熱負荷を受
けるプラズマ中心平面Bで冷却材流路のピツチが
最大となり、比較的熱負荷の小さい上部あるいは
下部でピツチが最小となるので、冷却むらが起
り、構造材最高温度と構造材内部での熱応力を許
容値以下に抑えることが難しいこと、更に、第1
壁8を増殖ブランケツト容器とは独立の構造物と
して該ブランケツト容器の前方に設置した場合に
は第1壁8とブランケツト容器壁との両方で中性
子の減速吸収が起り、中性子経済が悪く、ブラン
ケツトのトリチウム増殖性能に悪影響を与えるこ
と、第1壁8の支持が厳しい熱負荷、粒子負荷の
条件下であるので難しいこと等の問題があり、そ
の解決がいそがれていた。
By the way, the first wall 8 of the tokamak type fusion reactor is
Conventionally, as shown in Fig. 2, cooling is performed by using a method in which the coolant flows in the poloidal direction, that is, in the direction of arrow A. However, because the shape is toroidal, the pitch of the coolant flow path is in the direction of the flow. The problem arises that it changes. In other words, the pitch of the coolant flow path is maximum at the plasma center plane B, which receives the severest heat load, and the pitch is minimum at the upper or lower part, where the heat load is relatively small, resulting in uneven cooling and the maximum temperature of the structural material. It is difficult to suppress the thermal stress inside the structural material below the allowable value, and
If the wall 8 is installed in front of the blanket container as a structure independent of the breeding blanket container, neutron deceleration and absorption will occur in both the first wall 8 and the wall of the blanket container, resulting in poor neutron economy and There are problems such as adverse effects on tritium breeding performance and difficulty in supporting the first wall 8 under severe heat load and particle load conditions, and it has been difficult to solve these problems.
そこで、本発明は、上記技術的な問題に鑑み、
冷却性能と中性子経済に優れた核融合炉の第1壁
の冷却構造を提供しようとするものである。 Therefore, in view of the above technical problems, the present invention has been made to
The objective is to provide a cooling structure for the first wall of a fusion reactor that has excellent cooling performance and neutron economy.
上記課題を解決するための本発明の核融合炉第
1壁の冷却構造は、箱形ブランケツトの容器壁と
第1壁とを一体化し、該第1壁に冷却材をトロイ
ダル方向に流す多数の冷却材流路を設け、この冷
却材流路を分配、集合し且つブランケツトの補強
フランジを兼ねる冷却材マニホルドをブランケツ
トの後側に少なくとも左右一対設け、この左右の
マニホルドの内部をポロイダル方向で左右段違い
に複数に分割し、該分割マニホルドにつながる冷
却材流路の本数を冷却材マニホルド下端の冷却材
入口側で多くとり、冷却材マニホルド上端の冷却
出口側で少なくとつて、冷却材を前記分割マニホ
ルドで順次折り返して冷却材流路内に送り込み、
第1壁を冷却するようにしたものである。
The cooling structure for the first wall of a fusion reactor according to the present invention for solving the above problems integrates the container wall of the box-shaped blanket and the first wall, and has a large number of channels that flow the coolant in a toroidal direction to the first wall. A coolant flow path is provided, and at least a pair of left and right coolant manifolds that distribute and collect the coolant flow path and also serve as reinforcing flanges for the blanket are provided on the rear side of the blanket, and the insides of the left and right manifolds are arranged at different levels on the left and right sides in the poloidal direction. The number of coolant passages connected to the divided manifold is increased on the coolant inlet side at the lower end of the coolant manifold, and is reduced on the cooling outlet side at the upper end of the coolant manifold, so that the coolant is routed through the divided manifold. The coolant is sequentially folded back and sent into the coolant flow path.
The first wall is cooled.
このように構成された本発明の核融合炉用第1
壁の冷却構造によれば、炉運転中冷却材が第1壁
のトロイダル方向に冷却材流路を分割マニホルド
を経由して、右から左へ、→左から右へ、→右か
ら左へ…と、順に流れるので、実質的な冷却材の
除熱流路長さが長くなる。また分割されたマニホ
ルドにつながる冷却材流路本数を冷却材入口側で
多くとり、冷却材出口側で少なくとつているの
で、冷却材流路の圧力損失が少なく、冷却材温度
の低い冷却材入口側の各冷却材流路における冷却
材の流速が小さくなつて流量が少なくなり、熱伝
達率が小さくなる。そして冷却材温度の高い冷却
材出口側の各冷却材流路における冷却材の流速が
大きくなつて流量が多くなり、熱伝達率が大きく
なる。従つて、冷却材流路の入口側と出口側の境
膜温度差が小さくなり、第1壁の構造材温度が抑
えられて平坦化し、熱変形、熱応力の発生が抑制
されると共に冷却材の沸騰が防止される。
The first nuclear fusion reactor of the present invention configured as described above
According to the wall cooling structure, during furnace operation, the coolant passes through the manifold that divides the coolant flow path in the toroidal direction of the first wall, from right to left, → left to right, → right to left... Since the coolant flows in this order, the actual heat removal flow path length of the coolant becomes longer. In addition, the number of coolant flow paths connected to the divided manifolds is increased on the coolant inlet side and fewer on the coolant outlet side, resulting in less pressure loss in the coolant flow path and a lower coolant temperature at the coolant inlet. The flow velocity of the coolant in each of the side coolant channels becomes smaller, the flow rate becomes smaller, and the heat transfer coefficient becomes smaller. Then, the flow velocity of the coolant in each coolant flow path on the coolant outlet side where the coolant temperature is high increases, the flow rate increases, and the heat transfer coefficient increases. Therefore, the film temperature difference between the inlet and outlet sides of the coolant flow path is reduced, and the temperature of the structural material of the first wall is suppressed and flattened, suppressing the occurrence of thermal deformation and thermal stress, and suppressing the coolant flow. boiling is prevented.
本発明の各融合炉用第1壁の冷却構造の一実施
例を図によつて説明する。第3図は箱形のブラン
ケツトの容器壁を兼ねる第1壁をもつ箱形ブラン
ケツトの断面を示すもので、10はブランケツト
の容器壁を兼ねる第1壁で、11は第1壁10を
冷却するために冷却材をトロイダル方向に流す冷
却材流路であり、ブランケツトの後側に設けられ
た補強フランジ12を兼ねる左右の一対のマニホ
ルド12a,12bに接続されている。
An embodiment of the cooling structure for the first wall for each fusion reactor according to the present invention will be described with reference to the drawings. FIG. 3 shows a cross section of a box-shaped blanket having a first wall that also serves as the container wall of the box-shaped blanket, where 10 is the first wall that also serves as the container wall of the blanket, and 11 is the first wall that cools the first wall 10. This is a coolant flow path through which coolant flows in a toroidal direction, and is connected to a pair of left and right manifolds 12a and 12b which also serve as reinforcing flanges 12 provided on the rear side of the blanket.
この左右一対のマニホルド12a,12bは、
内部が第4図の冷却系概念図に示す如くポロイダ
ル方向に左右段違いに複数、本例では3段に分割
され、この分割されたマニホルドにつながる冷却
材流路11は冷却材の流速(熱伝達率)を調整す
るために分割されたマニホルド毎にポロイダル方
向でその本数が変化せしめられている。即ち、マ
ニホルド12aの下端の冷却材入口16側では平
行する冷却材流路11の本数を多くとつて、冷却
材の流速(熱伝導率)を小さくし、マニホルド1
2bの上端の冷却材出口17側では平行する冷却
材流路11の本数が少なくとつて、冷却材の流速
(熱伝達率)を大きくするようにしている。 This pair of left and right manifolds 12a, 12b are
As shown in the conceptual diagram of the cooling system in Fig. 4, the interior is divided into a plurality of stages, three stages in this example, on the left and right in the poloidal direction. In order to adjust the ratio), the number of tubes is varied in the poloidal direction for each divided manifold. That is, on the coolant inlet 16 side at the lower end of the manifold 12a, the number of parallel coolant channels 11 is increased to reduce the flow velocity (thermal conductivity) of the coolant, and the manifold 1
On the coolant outlet 17 side at the upper end of 2b, the number of parallel coolant channels 11 is reduced to increase the flow velocity (heat transfer coefficient) of the coolant.
前記第1壁10と一体化されたブランケツト容
器の内部には、トリチウム増殖材13と中性子減
速材14が収納されており、これらが収納された
間には適当な間隔でポロイダル方向に冷却材が流
れるブランケツト冷却用の冷却材流路15が第1
壁10側で多く、後方にいくにしたがつて少なく
配置されている。 A tritium breeder material 13 and a neutron moderator 14 are stored inside the blanket container integrated with the first wall 10, and a coolant is applied in the poloidal direction at appropriate intervals between these materials. The coolant flow path 15 for cooling the blanket is the first
There are many on the wall 10 side, and fewer toward the rear.
次に上記の如く構成した本実施例の作用につい
て説明する。該融合炉におけるブランケツトの第
1壁10は直接プラズマからの厳しい熱負荷、粒
子負荷を受けるため、該第1壁10を十分に冷却
することを要する。 Next, the operation of this embodiment configured as described above will be explained. The first wall 10 of the blanket in the fusion reactor is directly subjected to a severe heat load and particle load from the plasma, so it is necessary to cool the first wall 10 sufficiently.
この第1壁10を冷却するために、炉運転中第
1壁10の冷却材流路11内に第4図の冷却系概
念図に示される右側のマニホルド12aの下端の
冷却材入口16から冷却材を導入すると、該冷却
材は分割されたマニホルドから冷却材流路11
の部分、を通つて左側のマニホルド12b内
の分割されたマニホルドに至る。冷却材はここ
で折り曲げられ、、を通つて右側のマニホル
ド12aの分割されたマニホルドに至る。この
ようにして冷却材はマニホルド12a,12b内
の分割されたマニホルドをヘツダとしてUターン
し、以後、を通つて分割されたマニホルド
でUターンし、、を通つて分割されたマニホ
ルドでUターンし、、を通つて左側のマニ
ホルド16bの上端の分割されたマニホルドに
至り、冷却材出口17から冷却材が矢印の如く出
ていく。 In order to cool the first wall 10, during the reactor operation, the coolant is supplied into the coolant passage 11 of the first wall 10 from the coolant inlet 16 at the lower end of the right manifold 12a as shown in the conceptual diagram of the cooling system in FIG. Upon introduction of the coolant, the coolant flows from the divided manifold to the coolant flow path 11.
, to reach the divided manifold in the left manifold 12b. The coolant is now folded and passes through to the segmented manifold of the right hand manifold 12a. In this way, the coolant makes a U-turn using the divided manifolds in the manifolds 12a and 12b as headers, then makes a U-turn at the divided manifold through , and then makes a U-turn at the divided manifold through . , , to the divided manifold at the upper end of the left manifold 16b, and the coolant exits from the coolant outlet 17 as shown by the arrow.
このように冷却材は、第1壁10の冷却材流路
11を右から左へ、→左から右へ、→右から左へ
…と、順に流れるので、実施的な冷却材の除熱流
路長さが長くなる。 In this way, the coolant flows through the coolant flow path 11 of the first wall 10 in order from right to left, → left to right, → right to left, etc., so that the actual coolant heat removal flow path is length becomes longer.
また分割されたマニホルドにつながる冷却材流
路11の本数を、冷却材入口16側で多くとり、
冷却材出口17側で少なくとつているので、冷却
材流路11の圧力損失が過大となることがなく、
冷却材温度の低い冷却材入口16側の各冷却材流
路11における冷却材の流速が小さくなつて、流
量が少なくなり、熱伝達率が小さくなる。そして
冷却材温度の高い冷却材出口17側の各冷却材流
路11における冷却材の流速が大きくなつて流量
が多くなり、熱伝達率が大きくなる。従つて、冷
却材流路11の入口側と出口側の境膜温度差が小
さくなり、第1壁10の構造材温度が抑えられて
平坦化し、熱変形、熱応力の発生が抑制されると
共に冷却材の沸騰が防止される。 In addition, the number of coolant channels 11 connected to the divided manifolds is increased on the coolant inlet 16 side,
Since the coolant is kept at least on the side of the coolant outlet 17, the pressure loss in the coolant flow path 11 does not become excessive.
The flow velocity of the coolant in each coolant channel 11 on the side of the coolant inlet 16 where the coolant temperature is low decreases, the flow rate decreases, and the heat transfer coefficient decreases. The flow velocity of the coolant in each coolant channel 11 on the side of the coolant outlet 17 where the coolant temperature is high increases, the flow rate increases, and the heat transfer coefficient increases. Therefore, the film temperature difference between the inlet side and the outlet side of the coolant flow path 11 is reduced, the temperature of the structural material of the first wall 10 is suppressed and flattened, and the generation of thermal deformation and thermal stress is suppressed. Coolant boiling is prevented.
然して、トカマク型核融合炉では第1壁10に
対する熱負荷はプラズマ中心平面で最も大きく、
第1壁10の上下ではかなり小さくなる分布を示
しているが、このような分布に対応して、ポロイ
ダル方向での第1壁構造材の温度を平均化するよ
う冷却材流路11の本数を選択することにより、
熱変形や熱応力の発生を減少できる。 However, in a tokamak-type fusion reactor, the thermal load on the first wall 10 is greatest at the plasma center plane;
Although the distribution shows a considerably smaller distribution above and below the first wall 10, the number of coolant channels 11 is changed in order to average the temperature of the first wall structural material in the poloidal direction in response to such a distribution. By selecting
The occurrence of thermal deformation and thermal stress can be reduced.
尚、冷却材流路11の断面形状は円形とは限ら
ず、必要に応じて楕円、半円、矩形等の形状を採
用することもでき、更には熱負荷分布によつてこ
れらの形状の流路を適当に組合せて使用すること
もできる。 Note that the cross-sectional shape of the coolant flow path 11 is not limited to a circular shape, but can also be shaped as an ellipse, semicircle, rectangle, etc., depending on the heat load distribution. Any suitable combination of channels may also be used.
以上の通り、本発明の核融合炉用第1壁の冷却
構造は、第1壁と箱形ブランケツトの容器壁とを
一体化し、この第1壁に多数の冷却材流路をトロ
イダル方向に設け、この冷却材流路をブランケツ
トの後側に少なくとも左右一対設けた補強フラン
ジを兼ねる冷却材マニホルドの分割マニホルドに
接続して、冷却材が折り返し流れる流路となし、
且つ分割マニホルドに接続する冷却材流路数をプ
ラズマからの熱負荷に対応するように設定してあ
るので、冷却材流路の入口側と出口側の境膜温度
差が小さくなり、第1壁の構造材温度が抑えられ
て平坦化され、熱変形、熱応力の発生が抑制され
ると共に冷却材の沸騰が防止されて、冷却性能と
中性子経済が向上するという効果がある。
As described above, the cooling structure of the first wall for a fusion reactor of the present invention integrates the first wall and the container wall of the box-shaped blanket, and provides a large number of coolant channels in the toroidal direction in the first wall. , the coolant flow path is connected to a divided manifold of a coolant manifold that also serves as reinforcing flanges provided at least one pair on the left and right on the rear side of the blanket to form a flow path for the coolant to flow in a folded manner;
In addition, since the number of coolant channels connected to the divided manifold is set to correspond to the heat load from the plasma, the film temperature difference between the inlet and outlet sides of the coolant channel is reduced, and the first wall This has the effect of suppressing and flattening the structural material temperature, suppressing the generation of thermal deformation and thermal stress, and preventing boiling of the coolant, improving cooling performance and neutron economy.
第1図はトカマク型核融合炉の概略を示す断面
図、第2図は外側ブランケツト/第1壁の概略形
状を示す斜視図、第3図は本発明による核融合炉
用第1壁の冷却構造の一実施例を示す箱形ブラン
ケツトの断面図、第4図はその第1壁の冷却構造
の冷却系概念図、第5図は第3図のA−A断面の
一部を示す斜視図である。
10……第1壁、11……冷却材流路、12…
…補強フランジ、12a,12b……冷却材マニ
ホルド。
Fig. 1 is a sectional view schematically showing a tokamak type fusion reactor, Fig. 2 is a perspective view showing a schematic shape of the outer blanket/first wall, and Fig. 3 is a cooling of the first wall for a fusion reactor according to the present invention. A sectional view of a box-shaped blanket showing an example of the structure, FIG. 4 is a conceptual diagram of the cooling system of the cooling structure of the first wall, and FIG. 5 is a perspective view showing a part of the A-A cross section of FIG. 3. It is. 10...first wall, 11...coolant channel, 12...
...Reinforcement flange, 12a, 12b... Coolant manifold.
Claims (1)
し、該第1壁に冷却材をトロイダル方向に流す多
数の冷却材流路を設け、この冷却材流路を分配、
集合し且つブランケツトの補強フランジを兼ねる
冷却材マニホルドをブランケツトの後側に少なく
とも左右一対設け、この左右のマニホルドの内部
をポロイダル方向で左右段違いに複数に分割し、
該分割マニホルドにつながる冷却材流路の本数を
冷却材マニホルド下端の冷却材入口側で多くと
り、冷却材マニホルド上端の冷却材出口側で少な
くとつて、冷却材を前記分割マニホルドで順次折
り返して冷却材流路内に送り込み、第1壁を冷却
するようにしたことを特徴とする核融合炉用第1
壁の冷却構造。1. Integrating the container wall of the box-shaped bracket and the first wall, providing a large number of coolant flow channels in which the coolant flows in a toroidal direction on the first wall, and distributing the coolant flow channels;
At least a pair of left and right coolant manifolds that gather together and also serve as reinforcing flanges for the blanket are provided on the rear side of the blanket, and the inside of the left and right manifolds is divided into a plurality of left and right steps in the poloidal direction,
The number of coolant flow paths connected to the divided manifold is increased at the coolant inlet side at the lower end of the coolant manifold, and decreased at the coolant outlet side at the upper end of the coolant manifold, and the coolant is sequentially folded back and cooled by the divided manifold. A first material for a nuclear fusion reactor, characterized in that the material is fed into a flow path to cool the first wall.
Wall cooling structure.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59013058A JPS60157071A (en) | 1984-01-27 | 1984-01-27 | Cooling structure of first wall for fusion reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59013058A JPS60157071A (en) | 1984-01-27 | 1984-01-27 | Cooling structure of first wall for fusion reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60157071A JPS60157071A (en) | 1985-08-17 |
| JPH0246919B2 true JPH0246919B2 (en) | 1990-10-17 |
Family
ID=11822524
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59013058A Granted JPS60157071A (en) | 1984-01-27 | 1984-01-27 | Cooling structure of first wall for fusion reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60157071A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB202020283D0 (en) * | 2020-12-21 | 2021-02-03 | Tokamak Energy Ltd | Divertor cooling |
-
1984
- 1984-01-27 JP JP59013058A patent/JPS60157071A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60157071A (en) | 1985-08-17 |
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