JPH0894781A - Coolant circulation device for fusion reactor - Google Patents

Coolant circulation device for fusion reactor

Info

Publication number
JPH0894781A
JPH0894781A JP6235095A JP23509594A JPH0894781A JP H0894781 A JPH0894781 A JP H0894781A JP 6235095 A JP6235095 A JP 6235095A JP 23509594 A JP23509594 A JP 23509594A JP H0894781 A JPH0894781 A JP H0894781A
Authority
JP
Japan
Prior art keywords
coolant
cooling
pipe
fusion reactor
return
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
JP6235095A
Other languages
Japanese (ja)
Inventor
Yoshinao Ookawa
慶直 大川
Hiromoto Okada
宏基 岡田
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.)
IHI Corp
Japan Atomic Energy Agency
Original Assignee
IHI Corp
Japan Atomic Energy Research Institute
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 IHI Corp, Japan Atomic Energy Research Institute filed Critical IHI Corp
Priority to JP6235095A priority Critical patent/JPH0894781A/en
Publication of JPH0894781A publication Critical patent/JPH0894781A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors

Abstract

PURPOSE: To remove the residual heat in heat receiver block connected with a cooling loop having caused an accident even in the case of loss-of-cooling capability in a part of the cooling loop owing to the accident. CONSTITUTION: Coolant supply pipes 10 of a plurality of cooling loops 14a, 14b and 14c, 14d connected to heat receiver blocks 3a, 3b, 3c and 3d of a fusion reactor are connected to each other with supply side connection pipes 19 and 23 provided with open/close valves 18 and 22 in the vicinity of the heat receiver blocks 3a, 3b, 3c and 3d. Simultaneously, coolant return pipes 12 are connected to each other with the return side connection pipes 21 and 25 in the vicinity of the heat receiver blocks 3a, 3b, 3c and 3d. Also, at the position in a heat exchanger 13 close to the connection part of each connection pipes 19, 21, 23 and 25 in the coolant supply pipes 10 and the coolant return pipes 12, switch valves 26a, 27a, 26b, 27b, 26c, 27c, 26d and 27d are arranged.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、核融合炉の冷却材循環
装置に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a coolant circulating device for a fusion reactor.

【0002】[0002]

【従来の技術】図3は核融合炉の一例を示したもので、
中心にソレノイドコイル1が設けられて、その外周に、
夫々図示しない冷却材循環装置に接続された内側ブラン
ケット2、外側ブランケット3、及びダイバータ4等か
らなる受熱装置5が配置されており、該受熱装置5の外
周には、プラズマをプラズマ空間6に閉じ込めるための
トロイダルコイル7及びポロイダルコイル8が配設され
ている。
2. Description of the Related Art FIG. 3 shows an example of a fusion reactor.
The solenoid coil 1 is provided in the center, and on the outer periphery of it,
A heat receiving device 5 including an inner blanket 2, an outer blanket 3, and a diverter 4 connected to a coolant circulating device (not shown) is arranged, and plasma is confined in a plasma space 6 on the outer periphery of the heat receiving device 5. A toroidal coil 7 and a poloidal coil 8 are provided for this purpose.

【0003】前記受熱装置5を構成する内側ブランケッ
ト2、外側ブランケット3、及びダイバータ4等は、夫
々別個に冷却されるようになっており、これらの各内側
ブランケット2、外側ブランケット3、及びダイバータ
4は、図4及び図5に外側ブランケット3を例に取って
示すように、周方向に複数に区画した受熱部ブロック3
a,3b,3c,3dを構成しており、該各受熱部ブロ
ック3a,3b,3c,3dの夫々に、ポンプ9により
冷却材供給管10を介して冷却水或いはヘリウム等の冷
却材11を供給し、受熱部ブロック3a,3b,3c,
3dで加熱された冷却材11を冷却材戻し管12を介し
てボイラ或いは中間熱交換器等の熱交換器13に戻して
循環させるようにした冷却ループ14a,14b,14
c,14dを備えるようにしている。図中15は、ボイ
ラからなる熱交換器13に接続されたタービン発電機、
16は冷却ループ14a,14b,14c,14dに備
えた加圧器を示す。
The inner blanket 2, the outer blanket 3, the diverter 4 and the like which constitute the heat receiving device 5 are designed to be cooled separately, and the inner blanket 2, the outer blanket 3 and the diverter 4 are individually cooled. As shown by taking the outer blanket 3 as an example in FIGS. 4 and 5, the heat receiving part block 3 is divided into a plurality in the circumferential direction.
a, 3b, 3c, 3d, and each of the heat receiving unit blocks 3a, 3b, 3c, 3d is provided with a coolant 11 such as cooling water or helium via a coolant supply pipe 10 by a pump 9. Supply, heat receiving block 3a, 3b, 3c,
Cooling loops 14a, 14b, 14 for returning the coolant 11 heated in 3d to the heat exchanger 13 such as a boiler or an intermediate heat exchanger via the coolant return pipe 12 and circulating the coolant.
c and 14d are provided. In the figure, 15 is a turbine generator connected to the heat exchanger 13 composed of a boiler,
Reference numeral 16 denotes a pressurizer provided in the cooling loops 14a, 14b, 14c, 14d.

【0004】また、前記各冷却ループ14a,14b,
14c,14dには、核融合炉の通常運転停止後の受熱
装置5の残留熱を除去するための補助冷却器17を備え
るようにしている。尚、前記した内側ブランケット2及
びダイバータ4も周方向に複数のブロックに区画され、
前記外側ブランケット3と同様に受熱部ブロック毎に冷
却ループを備えて冷却を行うようになっている。
The cooling loops 14a, 14b,
14c and 14d are provided with an auxiliary cooler 17 for removing the residual heat of the heat receiving device 5 after the normal shutdown of the fusion reactor. The inner blanket 2 and the diverter 4 described above are also divided into a plurality of blocks in the circumferential direction,
Similar to the outer blanket 3, each heat receiving unit block is provided with a cooling loop for cooling.

【0005】核融合炉の通常運転時は、各冷却ループ1
4a,14b,14c,14dのポンプ9の作動により
冷却材11が受熱部ブロック3a,3b,3c,3dに
供給されてプラズマによる崩壊熱を除去し、加熱された
冷却材11を熱交換器13に循環して冷却するようにし
ている。
During normal operation of the fusion reactor, each cooling loop 1
The coolant 11 is supplied to the heat receiving block 3a, 3b, 3c, 3d by the operation of the pump 9 of 4a, 14b, 14c, 14d to remove the decay heat due to the plasma, and the heated coolant 11 is transferred to the heat exchanger 13. It is circulated in and cooled.

【0006】上記従来の核融合炉の冷却材循環装置にお
いて、一部の冷却ループ、例えば冷却ループ14aの熱
交換器13等に事故が発生して熱交換器13による冷却
が不能になった場合には、直ちに核融合炉を停止させる
が、核融合炉を停止しても受熱装置5には大きな残留熱
が存在しており、このような事故発生時における核融合
炉の残留熱の除去については現在検討されておらず、従
ってこのような事故発生時には、前記核融合炉の通常運
転停止後の残留熱を除去するようにしている補助冷却器
17を用いて残留熱の除去を行うことになる。
[0006] In the conventional coolant circulating device for a fusion reactor, when an accident occurs in a part of the cooling loop, for example, the heat exchanger 13 of the cooling loop 14a, and the cooling by the heat exchanger 13 becomes impossible. Will immediately stop the nuclear fusion reactor, but even if the nuclear fusion reactor is stopped, there is still a large amount of residual heat in the heat receiving device 5. Regarding the removal of the residual heat of the nuclear fusion reactor at the time of such an accident, Is not currently considered, and therefore, in the event of such an accident, removal of residual heat by using an auxiliary cooler 17 that removes the residual heat after the normal shutdown of the fusion reactor is decided. Become.

【0007】[0007]

【発明が解決しようとする課題】しかし、前記従来の核
融合炉の冷却材循環装置では、前記冷却材供給管10及
び冷却材戻し管12の破断、或いは図示しない弁の損傷
等の事故の発生により冷却ループ14a,14b,14
c,14dの一部が冷却能力を喪失した時には、前記補
助冷却器17によって残留熱を除去することが不可能と
なってしまう問題を有していた。
However, in the conventional coolant circulating device of the fusion reactor, an accident such as breakage of the coolant supply pipe 10 and the coolant return pipe 12 or damage of a valve not shown occurs. The cooling loops 14a, 14b, 14
When a part of c and 14d loses the cooling capacity, there is a problem that it becomes impossible to remove the residual heat by the auxiliary cooler 17.

【0008】本発明は、斯かる実情に鑑みてなしたもの
で、冷却ループの一部が事故によって冷却能力を喪失し
た場合にも、事故を起こした冷却ループに接続されてい
る受熱部ブロックの残留熱を除去することができるよう
にした核融合炉の冷却材循環装置を提供することを目的
としている。
The present invention has been made in view of the above circumstances, and even when a part of the cooling loop loses its cooling capacity due to an accident, the heat receiving unit block connected to the cooling loop in which the accident occurred It is an object of the present invention to provide a coolant circulating device for a fusion reactor capable of removing residual heat.

【0009】[0009]

【課題を解決するための手段】本発明は、核融合炉の周
方向に配設される受熱部ブロックごとに冷却材供給管を
介して冷却材を供給し、加熱された冷却材を冷却材戻し
管を介して熱交換器に循環させる冷却ループを備えた核
融合炉の冷却材循環装置であって、複数の冷却ループの
冷却材供給管同士を開閉弁を備えた供給側連絡管により
受熱部ブロックに近い位置で接続すると共に、前記複数
の冷却ループの冷却材戻し管同士を開閉弁を備えた戻し
側連絡管により受熱部ブロックに近い位置で接続し、且
つ前記冷却材供給管及び冷却材戻し管における前記各連
絡管接続部に近い熱交換器側位置に切換弁を配設したこ
とを特徴とする核融合炉の冷却材循環装置、及び、供給
側連絡管及び戻し側連絡管が環状を有していることを特
徴とする核融合炉の冷却材循環装置、に係るものであ
る。
According to the present invention, a coolant is supplied through a coolant supply pipe for each heat receiving section block arranged in the circumferential direction of a fusion reactor, and the heated coolant is used as a coolant. A coolant circulation device for a fusion reactor having a cooling loop that circulates to a heat exchanger via a return pipe, wherein the coolant supply pipes of a plurality of cooling loops receive heat by a supply-side connecting pipe equipped with an on-off valve. Part of the cooling loop, the cooling material return pipes of the plurality of cooling loops are connected to each other at a position close to the heat receiving part block by a return side connecting pipe having an opening / closing valve, and the cooling material supply pipe and the cooling A coolant circulating device of a fusion reactor, characterized in that a switching valve is arranged at a position on the heat exchanger side in the material return pipe close to each connecting pipe connecting portion, and a supply side connecting pipe and a returning side connecting pipe. Fusion reactor characterized by having an annular shape Coolant circulation system, in which according to the.

【0010】[0010]

【作用】請求項1及び2の発明では、受熱部を複数に区
画した受熱部ブロックの夫々に接続されている複数の冷
却ループの冷却材供給管同士を開閉弁を備えた供給側連
絡管(又は環状供給側連絡管)により接続すると共に、
複数の冷却ループの冷却材戻し管同士を開閉弁を備えた
戻し側連絡管(又は環状戻し側連絡管)により接続し、
前記冷却材供給管及び冷却材戻し管における各連絡管接
続部に近い熱交換器側位置に切換弁を配置した構成を有
しているので、冷却材供給管及び冷却材戻し管の破断や
弁の損傷等の事故の発生により一部の冷却ループが冷却
能力を喪失した時、事故が発生した冷却ループに接続さ
れている受熱部ブロックを別の冷却ループに連通させ、
これにより事故が発生した冷却ループに接続されている
受熱部ブロックの残留熱を別の冷却ループで兼用して安
全に除去することができる。
According to the first and second aspects of the invention, the coolant supply pipes of the plurality of cooling loops connected to each of the heat receiving part blocks in which the heat receiving part is divided into a plurality of parts are connected to each other on the supply side connecting pipe (opening valve). Or the connection pipe of the annular supply side)
The coolant return pipes of a plurality of cooling loops are connected to each other by a return side communication pipe (or an annular return side communication pipe) equipped with an on-off valve
Since the switching valve is arranged at the heat exchanger side position near each connecting pipe connection part in the coolant supply pipe and the coolant return pipe, the coolant supply pipe and the coolant return pipe are broken or the valve is provided. When a part of the cooling loop loses its cooling capacity due to the occurrence of an accident such as damage to the heat receiving part block connected to the cooling loop where the accident occurred to another cooling loop,
As a result, the residual heat of the heat receiving block connected to the cooling loop where the accident occurs can be shared by another cooling loop and safely removed.

【0011】[0011]

【実施例】以下、本発明の実施例を図面を参照しつつ説
明する。
Embodiments of the present invention will be described below with reference to the drawings.

【0012】図3に示したように核融合炉の周方向に配
設される内側ブランケット2、外側ブランケット3、及
びダイバータ4等からなる受熱装置5のうち、外側ブラ
ンケット3を例にとって示した図1について説明する
と、複数に区画された受熱部ブロック3a,3b,3
c,3dごとに、冷却材供給管10を介して冷却材11
を供給し、加熱された冷却材11を冷却材戻し管12を
介して熱交換器13に循環させる冷却ループ14a,1
4b,14c,14dを備えている。
As shown in FIG. 3, the outer blanket 3 is shown as an example of the heat receiving device 5 including the inner blanket 2, the outer blanket 3 and the diverter 4 arranged in the circumferential direction of the fusion reactor. 1, the heat receiving section blocks 3a, 3b, 3 divided into a plurality of sections will be described.
For each of c and 3d, the coolant 11 is provided through the coolant supply pipe 10.
Cooling loops 14a, 1 for circulating the heated coolant 11 to the heat exchanger 13 via the coolant return pipe 12
4b, 14c, 14d.

【0013】隣接する2つの冷却ループ14aと14b
の冷却材供給管10,10同士を、受熱部ブロック3
a,3bに近い位置で開閉弁18を備えた供給側連絡管
19によって接続すると共に、冷却材戻し管12,12
同士を、前記受熱部ブロック3a,3bに近い位置で開
閉弁20を備えた戻し側連絡管21により接続する。
Two adjacent cooling loops 14a and 14b
The coolant supply pipes 10 and 10 of the
a and 3b are connected by a supply-side communication pipe 19 equipped with an on-off valve 18, and coolant return pipes 12, 12 are provided.
The two are connected to each other by a return side connecting pipe 21 equipped with an on-off valve 20 at a position close to the heat receiving block 3a, 3b.

【0014】隣接する2つの冷却ループ14cと14d
の冷却材供給管10,10同士を、受熱部ブロック3
c,3dに近い位置で開閉弁22を備えた供給側連絡管
23によって接続すると共に、冷却材戻し管12,12
同士を、前記受熱部ブロック3c,3dに近い位置で開
閉弁24を備えた戻し側連絡管25により接続する。
Two adjacent cooling loops 14c and 14d
The coolant supply pipes 10 and 10 of the
c, 3d are connected by a supply-side communication pipe 23 equipped with an on-off valve 22 at a position close to
The two are connected to each other by a return side connecting pipe 25 having an opening / closing valve 24 at a position close to the heat receiving block 3c, 3d.

【0015】また、前記各冷却材供給管10及び冷却材
戻し管12における前記連絡管19,21,23,25
の接続部に近接した熱交換器13側位置に、切換弁26
a,27a、26b,27b、26c,27c、26
d,27dを配設する。
Further, the connecting pipes 19, 21, 23, 25 in each of the coolant supply pipe 10 and the coolant return pipe 12 are connected.
At the heat exchanger 13 side position close to the connection part of the switching valve 26
a, 27a, 26b, 27b, 26c, 27c, 26
d and 27d are provided.

【0016】前記開閉弁18,20,22,24及び切
換弁26a,27a、26b,27b、26c,27
c、26d,27dは、図示しない制御装置によって自
動的に開閉が制御されるように構成されている。
The on-off valves 18, 20, 22, 24 and the switching valves 26a, 27a, 26b, 27b, 26c, 27.
Opening and closing of c, 26d, and 27d are automatically controlled by a controller (not shown).

【0017】次に上記実施例の作用を説明する。Next, the operation of the above embodiment will be described.

【0018】上記実施例では、核融合炉の通常の運転時
は、各連絡管19,21,23,25の開閉弁18,2
0,22,24は閉じられ、切換弁26a,27a、2
6b,27b、26c,27c、26d,27dは開け
られた状態に保持されていて、複数の受熱部ブロック3
a,3b,3c,3dは夫々の冷却ループ14a,14
b,14c,14dによって独立して冷却されている。
In the above embodiment, the opening / closing valves 18, 2 of the connecting pipes 19, 21, 23, 25 are operated during normal operation of the fusion reactor.
0, 22, 24 are closed, and the switching valves 26a, 27a, 2
6b, 27b, 26c, 27c, 26d, 27d are held in an open state, and the plurality of heat receiving unit blocks 3
a, 3b, 3c, 3d are cooling loops 14a, 14 respectively
It is independently cooled by b, 14c and 14d.

【0019】上記構成において、冷却材供給管10及び
冷却材戻し管12の破断や弁の損傷等の事故の発生によ
り一部の冷却ループが冷却能力を喪失した時でも、別の
冷却ループに接続することによって、事故が発生した冷
却ループに接続されている受熱部の残留熱を別の冷却ル
ープで兼用して除去することができる。
In the above structure, even when some cooling loops lose their cooling ability due to an accident such as breakage of the coolant supply pipe 10 and the coolant return pipe 12 or damage to the valve, they are connected to another cooling loop. By doing so, it is possible to remove the residual heat of the heat receiving portion connected to the cooling loop in which the accident has occurred by using it in another cooling loop.

【0020】即ち、図1において冷却ループ14aに事
故が発生した場合を例に取って説明すると、事故が発生
した場合には核融合炉は運転を停止されるが、これと同
時に、切換弁26a,27aを閉じて冷却材11が熱交
換器13側に流れるのを阻止すると共に、開閉弁18,
20を開くことにより、冷却ループ14bの冷却材供給
管10の冷却材11を、事故が発生した冷却ループ14
aが接続されている受熱部ブロック3aに供給し、該受
熱部ブロック3aにて加熱された冷却材11を前記冷却
ループ14bの冷却材戻し管12に戻すようにする。
That is, the case where an accident occurs in the cooling loop 14a in FIG. 1 will be described as an example. When an accident occurs, the fusion reactor is stopped, but at the same time, the switching valve 26a is operated. , 27a are closed to prevent the coolant 11 from flowing to the heat exchanger 13 side, and the open / close valve 18,
By opening 20, the coolant 11 of the coolant supply pipe 10 of the cooling loop 14b is replaced with the coolant loop 14 in which the accident has occurred.
a is supplied to the heat receiving unit block 3a connected to the heat receiving unit block 3a, and the coolant 11 heated by the heat receiving unit block 3a is returned to the coolant return pipe 12 of the cooling loop 14b.

【0021】これにより、事故が発生した冷却ループ1
4aが接続されている受熱部ブロック3aの残留熱を、
隣接する別の冷却ループ14bによって確実に除去し
て、核融合炉の安全性を高めることができる。
As a result, the cooling loop 1 in which the accident has occurred
4a is connected to the heat receiving block 3a residual heat,
It can be reliably removed by another adjacent cooling loop 14b to enhance the safety of the fusion reactor.

【0022】図2は本発明の他の実施例を示したもの
で、環状に構成される受熱部ブロック3a,3b,3
c,3dに沿うように環状に形成した環状供給側連絡管
28と環状戻し側連絡管29を配設し、該環状供給側連
絡管28を複数の各冷却ループ14a,14b,14
c,14dの冷却材供給管10に接続すると共に、環状
戻し側連絡管29を複数の各冷却材戻し管12に接続
し、前記環状供給側連絡管28及び環状戻し側連絡管2
9の夫々に、任意の冷却ループ14a,14b,14
c,14d同士を連通できるように開閉弁28a,28
b,28c,28d及び29a,29b,29c,29
dを配設する。
FIG. 2 shows another embodiment of the present invention, in which the heat receiving section blocks 3a, 3b, 3 formed in an annular shape.
An annular supply-side communication pipe 28 and an annular return-side communication pipe 29, which are formed annularly along c and 3d, are arranged, and the annular supply-side communication pipe 28 is connected to the plurality of cooling loops 14a, 14b, 14 respectively.
In addition to being connected to the coolant supply pipes 10 of c and 14d, the annular return side communication pipe 29 is connected to each of the plurality of coolant return pipes 12, and the annular supply side communication pipe 28 and the annular return side communication pipe 2 are connected.
Each of the nine cooling loops 14a, 14b, 14
Open / close valves 28a, 28 so that c and 14d can communicate with each other.
b, 28c, 28d and 29a, 29b, 29c, 29
Arrange d.

【0023】上記図2の実施例では、冷却ループの一
部、例えは冷却ループ14aが事故によって冷却能力を
喪失した場合に、事故が発生した冷却ループ14aを他
の冷却ループ14b又は14c又は14dの何れか1つ
と接続するか、或いは冷却ループ14bと14c、又は
14cと14dのように2つと接続するか、或いは14
a〜14dの3つに接続して、事故が発生した冷却ルー
プ14aの受熱部ブロック3aの残留熱を他の任意の冷
却ループで除去(或いは複数の冷却ループで分担して除
去)し、核融合炉の安全性を高めることができる。
In the embodiment of FIG. 2 described above, when a part of the cooling loop, for example, the cooling loop 14a loses its cooling capacity due to an accident, the cooling loop 14a in which the accident has occurred is replaced with another cooling loop 14b or 14c or 14d. Or one of two cooling loops 14b and 14c, or 14c and 14d, or 14
a to 14d, the residual heat of the heat receiving block 3a of the cooling loop 14a in which the accident has occurred is removed by another arbitrary cooling loop (or is shared by a plurality of cooling loops) and removed. The safety of the fusion reactor can be improved.

【0024】[0024]

【発明の効果】請求項1及び2の発明によれば、一部の
冷却ループが事故によって冷却能力を喪失しても、事故
が発生した冷却ループに接続されている受熱部ブロック
を別の冷却ループに接続して、事故が発生した冷却ルー
プに接続されている受熱部ブロックの残留熱を別の冷却
ループで兼用して除去することができるので、冷却ルー
プの事故発生時における核融合炉の安全性を高めること
がきる優れた効果を奏し得る。
According to the first and second aspects of the present invention, even if a part of the cooling loop loses its cooling capacity due to an accident, the heat receiving block connected to the cooling loop in which the accident has occurred is cooled separately. By connecting to the loop, the residual heat of the heat receiving block connected to the cooling loop where the accident occurred can be removed by another cooling loop as well. An excellent effect of enhancing safety can be achieved.

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

【図1】本発明の一実施例を示す平面図である。FIG. 1 is a plan view showing an embodiment of the present invention.

【図2】本発明の他の実施例を示す斜視図である。FIG. 2 is a perspective view showing another embodiment of the present invention.

【図3】核融合炉の一例を示す一部切断斜視図である。FIG. 3 is a partially cutaway perspective view showing an example of a nuclear fusion reactor.

【図4】従来の核融合炉の冷却材循環装置の一部を示す
斜視図である。
FIG. 4 is a perspective view showing a part of a coolant circulating device of a conventional fusion reactor.

【図5】従来の核融合炉の冷却材循環装置の一例を示す
平面図である。
FIG. 5 is a plan view showing an example of a conventional coolant circulating device for a fusion reactor.

【符号の説明】[Explanation of symbols]

3a 受熱部ブロック 3b 受熱部ブロック 3c 受熱部ブロック 3d 受熱部ブロック 10 冷却材供給管 11 冷却材 12 冷却材戻し管 13 熱交換器 14a 冷却ループ 14b 冷却ループ 14c 冷却ループ 14d 冷却ループ 18 開閉弁 19 供給側連絡管 20 開閉弁 21 戻し側連絡管 22 開閉弁 23 供給側連絡管 24 開閉弁 25 戻し側連絡管 26a 切換弁 26b 切換弁 26c 切換弁 26d 切換弁 27a 切換弁 27b 切換弁 27c 切換弁 27d 切換弁 28 環状供給側連絡管 28a 開閉弁 28b 開閉弁 28c 開閉弁 28d 開閉弁 29 戻し側連絡管 29a 開閉弁 29b 開閉弁 29c 開閉弁 29d 開閉弁 3a Heat receiving part block 3b Heat receiving part block 3c Heat receiving part block 3d Heat receiving part block 10 Coolant supply pipe 11 Coolant 12 Coolant return pipe 13 Heat exchanger 14a Cooling loop 14b Cooling loop 14c Cooling loop 14d Cooling loop 18 Opening valve 19 Supply Side connecting pipe 20 Open / close valve 21 Return side connecting pipe 22 Open / close valve 23 Supply side connecting pipe 24 Open / close valve 25 Return side connecting pipe 26a Change valve 26b Change valve 26c Change valve 26d Change valve 27a Change valve 27b Change valve 27c Change valve 27d Change valve Valve 28 Annular supply side communication pipe 28a Open / close valve 28b Open / close valve 28c Open / close valve 28d Open / close valve 29 Return side communication pipe 29a Open / close valve 29b Open / close valve 29c Open / close valve 29d Open / close valve

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】 核融合炉の周方向に配設される受熱部ブ
ロックごとに冷却材供給管を介して冷却材を供給し、加
熱された冷却材を冷却材戻し管を介して熱交換器に循環
させる冷却ループを備えた核融合炉の冷却材循環装置で
あって、複数の冷却ループの冷却材供給管同士を開閉弁
を備えた供給側連絡管により受熱部ブロックに近い位置
で接続すると共に、前記複数の冷却ループの冷却材戻し
管同士を開閉弁を備えた戻し側連絡管により受熱部ブロ
ックに近い位置で接続し、且つ前記冷却材供給管及び冷
却材戻し管における前記各連絡管接続部に近い熱交換器
側位置に切換弁を配設したことを特徴とする核融合炉の
冷却材循環装置。
1. A coolant is supplied through a coolant supply pipe to each heat receiving unit block arranged in the circumferential direction of a fusion reactor, and the heated coolant is passed through a coolant return pipe to a heat exchanger. A coolant circulating device for a nuclear fusion reactor having a cooling loop for circulation to a plurality of cooling loops, wherein the coolant supplying pipes of a plurality of cooling loops are connected to each other at a position close to the heat receiving block by a supply side connecting pipe having an on-off valve. Along with, the coolant return pipes of the plurality of cooling loops are connected to each other at a position close to the heat receiving section block by a return side communication pipe provided with an on-off valve, and the communication pipes in the coolant supply pipe and the coolant return pipe. A coolant circulating device for a fusion reactor, wherein a switching valve is arranged at a position on the heat exchanger side near the connecting portion.
【請求項2】 供給側連絡管及び戻し側連絡管が環状を
有していることを特徴とする請求項1に記載の核融合炉
の冷却材循環装置。
2. The coolant circulation device for a nuclear fusion reactor according to claim 1, wherein the supply-side communication pipe and the return-side communication pipe have an annular shape.
JP6235095A 1994-09-29 1994-09-29 Coolant circulation device for fusion reactor Pending JPH0894781A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6235095A JPH0894781A (en) 1994-09-29 1994-09-29 Coolant circulation device for fusion reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6235095A JPH0894781A (en) 1994-09-29 1994-09-29 Coolant circulation device for fusion reactor

Publications (1)

Publication Number Publication Date
JPH0894781A true JPH0894781A (en) 1996-04-12

Family

ID=16980992

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6235095A Pending JPH0894781A (en) 1994-09-29 1994-09-29 Coolant circulation device for fusion reactor

Country Status (1)

Country Link
JP (1) JPH0894781A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110739086A (en) * 2019-10-22 2020-01-31 中国科学院合肥物质科学研究院 auxiliary loop for Tokamak fusion device cooling power generation system

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110739086A (en) * 2019-10-22 2020-01-31 中国科学院合肥物质科学研究院 auxiliary loop for Tokamak fusion device cooling power generation system

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