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JPS5953518B2 - Device for reducing hydrogen isotope permeation in piping systems of gas-cooled nuclear reactors and fusion reactors - Google Patents
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JPS5953518B2 - Device for reducing hydrogen isotope permeation in piping systems of gas-cooled nuclear reactors and fusion reactors - Google Patents

Device for reducing hydrogen isotope permeation in piping systems of gas-cooled nuclear reactors and fusion reactors

Info

Publication number
JPS5953518B2
JPS5953518B2 JP53009098A JP909878A JPS5953518B2 JP S5953518 B2 JPS5953518 B2 JP S5953518B2 JP 53009098 A JP53009098 A JP 53009098A JP 909878 A JP909878 A JP 909878A JP S5953518 B2 JPS5953518 B2 JP S5953518B2
Authority
JP
Japan
Prior art keywords
gas
hydrogen isotope
reactors
pipe
hydrogen
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
Application number
JP53009098A
Other languages
Japanese (ja)
Other versions
JPS54102500A (en
Inventor
克己 安福
敏公 黒田
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.)
Kawasaki Heavy Industries Ltd
Original Assignee
Kawasaki Heavy Industries Ltd
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 Kawasaki Heavy Industries Ltd filed Critical Kawasaki Heavy Industries Ltd
Priority to JP53009098A priority Critical patent/JPS5953518B2/en
Publication of JPS54102500A publication Critical patent/JPS54102500A/en
Publication of JPS5953518B2 publication Critical patent/JPS5953518B2/en
Expired 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
    • 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
    • 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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physical Or Chemical Processes And Apparatus (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)

Description

【発明の詳細な説明】 本発明は、ガス冷却型原子炉及び核融合炉の配管系に於
ける水素同位体の透過量減少装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a device for reducing the amount of permeation of hydrogen isotopes in piping systems of gas-cooled nuclear reactors and nuclear fusion reactors.

例えば核融合炉ブランケットの材料としてLi。For example, Li is used as a material for fusion reactor blankets.

Oなどが使用され、冷却材としてHeガスが用いられる
配管系特に冷却材一次循環ループ内に於いては、生成さ
れた水素同位体(H。、D。、T2)が不純物としてH
eガス中に存在する。この水素同位体の内、T。は約1
2.5年の半減期を有する放射性不純物であり、しかも
これら水素同位体は高温の場合金属壁を透過して格納容
器内や冷却材二次循環ループに流出する性質があるので
、もし格納容器内や冷却材二次循環ループに流出した場
合には大気の放射能汚染による公害の発生する恐れがあ
る。また前記T。はそれ自身が核燃料となる為、できる
限り回収する必要がある。従来、水素同位体をガス冷却
型原子炉及び核融合炉の冷却材一次循環ループ沖から除
去回収する方法としては、チタン金属に吸収させる方法
や、酸化触媒塔を用い水素同位体を水に変換させた後吸
湿材に吸着させる方法があるが、これらの方法では冷却
材一次循環ループの配管からの水素同位体の透過を低減
できないし、また塔自体が大きなものとなる。
In piping systems where O gas is used and He gas is used as a coolant, especially in the coolant primary circulation loop, the generated hydrogen isotopes (H., D., T2) become H as impurities.
Exists in e-gas. Among these hydrogen isotopes, T. is about 1
They are radioactive impurities with a half-life of 2.5 years, and these hydrogen isotopes have the property of penetrating metal walls at high temperatures and leaking into the containment vessel and the secondary coolant circulation loop. If it leaks into the interior or the secondary coolant circulation loop, there is a risk of pollution due to radioactive contamination of the atmosphere. Also, the above T. Because it itself becomes nuclear fuel, it is necessary to recover as much as possible. Conventional methods for removing and recovering hydrogen isotopes from the primary coolant circulation loop of gas-cooled nuclear reactors and nuclear fusion reactors include absorbing them into titanium metal, and converting hydrogen isotopes into water using oxidation catalyst towers. There is a method of adsorbing the hydrogen isotope on a moisture absorbing material after the hydrogen isolating, but these methods cannot reduce the permeation of hydrogen isotopes from the piping of the primary coolant circulation loop, and the tower itself becomes large.

この為格納容器を拡大しなければならないの′で、ガス
冷却型原子炉及び核融合炉プラントが大規模なものとな
り、設置費用が厖大となるものである。
For this reason, the containment vessel must be expanded, making the gas-cooled nuclear reactor and nuclear fusion reactor plant large-scale, and the installation cost becomes enormous.

本発明はかかる実状に鑑みてなされたものであり、従来
の酸化触媒塔や水素同位体除去塔を設けワることなく、
既設の配管内で水素同位体をできるだけ水に変換させ、
水素同位体ガス分圧を低減し、配管からの水素同位体の
透過量を減少するようにした装置を提供せんとするもの
である。
The present invention was made in view of the above circumstances, and it is possible to eliminate the need for conventional oxidation catalyst towers and hydrogen isotope removal towers.
Convert as much hydrogen isotope as possible to water within existing piping,
It is an object of the present invention to provide a device that reduces the partial pressure of hydrogen isotope gas and reduces the amount of hydrogen isotope permeated through piping.

本発明による水素同位体の透過量減少装置は、フガス冷
却型原子炉及び核融合炉の配管系に於いて、少くとも冷
却材一次循環ループの炉心出口から蓄熱器を含む中間熱
交換器の入口に至る配管の内面に、白金、パラジウム等
の酸化触媒をコーティングするか又は前記酸化触媒の網
を張設すると5共に、その配管の炉心出口附近及び炉心
を迂回するバイパス管の途中に夫々酸素供給系を接続し
て成るものである。以下その実施例を核融合炉の場合を
図面に基いて説明すると、第1図は核融合炉の配管系に
於ける冷却材一次循環ループの概略を示すもので、冷却
材であるHeガスは炉心1を通つて高温となり、蓄熱器
2を経て中間熱交換器3に入つて図示せぬ冷却材二次循
環ループの冷却材であるHeガスと熱交換し、温度降下
した冷却材一次循環ループのHeガスはプロア一4に、
より再び炉心1に送られる。
The hydrogen isotope permeation amount reducing device according to the present invention is used in piping systems of fugas-cooled nuclear reactors and nuclear fusion reactors, from at least the core outlet of the coolant primary circulation loop to the inlet of an intermediate heat exchanger including a heat storage device. If the inner surface of the piping leading to the reactor is coated with an oxidation catalyst such as platinum or palladium, or a net of the oxidation catalyst is stretched, oxygen will be supplied to the piping near the reactor core exit and in the middle of the bypass pipe that detours around the reactor core. It is made up of connected systems. An example of this will be explained based on drawings in the case of a fusion reactor. Figure 1 shows an outline of the primary circulation loop of coolant in the piping system of a fusion reactor, and He gas as a coolant is The coolant primary circulation loop becomes high temperature through the reactor core 1, passes through the heat storage device 2, enters the intermediate heat exchanger 3, exchanges heat with He gas, which is the coolant of the coolant secondary circulation loop (not shown), and lowers the temperature. He gas is sent to Proa-14,
It is then sent to the core 1 again.

即ち一次冷却材であるHeガスは熱除去の為閉回路で循
環するようになつている。そして核融合炉のパルス運転
に伴う炉心ブランケツトへの熱衝撃を避ける為に一次冷
却材であるHeガスは周期的に炉心1を迂回するバイパ
ス管5を通して蓄熱器2に送るようにしてある。尚6は
水素同位体の分離回収部で、プロア一4によりHeガス
と共に吸引される水(後で詳述する)をHeガスと分離
し、さらに水素同位体を分離回収するものである。然し
て本発明による水素同位体の透過量減少装置は、前記冷
却材一次循環ループに於いて炉心1の出口から蓄熱器2
を含む中間熱交換器3の入口に至る配管7の内面に、白
金、パラジウム等の酸化触媒をコーテイングするか、又
は前記酸化触媒の網を張設し、配管7の炉心1の出口附
近及び炉心1を迂回するバイパス管5の途中に夫々酸素
供給系8,8″を接続して成るものである。
That is, He gas, which is the primary coolant, is circulated in a closed circuit for heat removal. In order to avoid thermal shock to the core blanket due to the pulse operation of the fusion reactor, He gas, which is a primary coolant, is periodically sent to the heat storage device 2 through a bypass pipe 5 that bypasses the core 1. Reference numeral 6 denotes a hydrogen isotope separation and recovery section, which separates water (described in detail later) that is sucked together with the He gas by the proa 1 4 from the He gas, and further separates and recovers the hydrogen isotope. However, in the hydrogen isotope permeation amount reduction device according to the present invention, in the primary coolant circulation loop, from the outlet of the core 1 to the regenerator 2.
An oxidation catalyst such as platinum or palladium is coated on the inner surface of the pipe 7 leading to the inlet of the intermediate heat exchanger 3 containing Oxygen supply systems 8 and 8'' are connected to the middle of a bypass pipe 5 that bypasses the oxygen supply system 1, respectively.

かかる本発明の水素同位体の透過量減少装置に於いて、
配管7の内面に、白金、パラジウム等の酸化触媒をコー
テイングしてある場合、炉心1を出て配管7を通る冷却
材であるHeガス中に存在する水素同位体と、酸素供給
系8から配管7内に注入された酸素は、配管7の内面に
向つて拡散していく。
In the hydrogen isotope permeation amount reducing device of the present invention,
If the inner surface of the pipe 7 is coated with an oxidation catalyst such as platinum or palladium, the hydrogen isotopes present in the He gas, which is the coolant that exits the core 1 and passes through the pipe 7, and the oxygen supply system 8 from the pipe The oxygen injected into the pipe 7 diffuses toward the inner surface of the pipe 7.

やがて配管7の内面、即ち酸化触媒に到達すると、その
触媒作用により水素同位体と酸素は水に変換される。こ
の水素同位体と酸素との反応を、トリチウムを例にとつ
て示すと次の通りである。このようにしてH2ガス中に
存在する水素同位体は配管7を通過する間に次第に水に
変換されるので、配管7内の水素同位体ガス分圧が低減
され、配管7からの水素同位体の透過量を減少できて、
格納容器内への水素同位体の流出は許容値以下に充分押
えることができる。
When the gas eventually reaches the inner surface of the pipe 7, that is, the oxidation catalyst, the hydrogen isotope and oxygen are converted into water by its catalytic action. The reaction between this hydrogen isotope and oxygen is shown below using tritium as an example. In this way, the hydrogen isotope present in the H2 gas is gradually converted to water while passing through the pipe 7, so the partial pressure of the hydrogen isotope gas in the pipe 7 is reduced, and the hydrogen isotope from the pipe 7 is The amount of permeation can be reduced,
The leakage of hydrogen isotopes into the containment vessel can be sufficiently suppressed to below the permissible value.

また配管7を通つて中間熱交換器3に入つたH2ガス中
にはごく僅かしか水素同位体が存在しないので、水素同
位体ガス分圧は極めて低く、中間熱交換器3の伝熱管を
透過して水素同位体が冷却材二次循環ループ側に流出す
る量はごく僅かで安全上支障のない程度のものである。
一方、配管7の内面に、白金、パラジウム等のl酸化触
媒で作つた網を張設してある場合、炉心]を出たH2ガ
ス中の水素同位体と酸素供給系8から注入された酸素は
、配管7内を共に流れ、酸化触媒の網に接した時点で、
その触媒作用により水素同位体と酸素は水に変換される
Furthermore, since there is very little hydrogen isotope in the H2 gas that entered the intermediate heat exchanger 3 through the pipe 7, the hydrogen isotope gas partial pressure is extremely low and permeates through the heat exchanger tubes of the intermediate heat exchanger 3. The amount of hydrogen isotope flowing out into the secondary coolant circulation loop is very small and does not pose a safety problem.
On the other hand, if a net made of an oxidation catalyst such as platinum or palladium is installed on the inner surface of the pipe 7, hydrogen isotopes in the H2 gas exiting the reactor core and oxygen injected from the oxygen supply system 8 flow together in the pipe 7, and when they come into contact with the oxidation catalyst network,
Its catalytic action converts hydrogen isotopes and oxygen into water.

こうしてH2ガス中の水素同位体は配管7を通過する間
に次第に水に変換されるので、配管7内の水素同位体ガ
ス分圧が低減され、配管7からの水素同位体の透過量を
減少できて、前記と同様の効果を奏する。
In this way, the hydrogen isotope in the H2 gas is gradually converted to water while passing through the pipe 7, so the partial pressure of the hydrogen isotope gas in the pipe 7 is reduced, and the amount of hydrogen isotope permeated from the pipe 7 is reduced. It has the same effect as above.

この場合配管7の内面に酸化触媒の網を張設しているの
で、配管7内の圧力損失が問題となるが、網のメツシユ
数を小さくするか、網の枚数を少なくすることで許容さ
れる圧力損失の値にすることが可能である。
In this case, since the oxidation catalyst network is stretched over the inner surface of the pipe 7, pressure loss inside the pipe 7 becomes a problem, but this can be overcome by reducing the number of meshes or the number of meshes in the pipe 7. It is possible to set the pressure drop to a value that

また逆に水素同位体の酸化率を上げたい場合、換言すれ
ばより一層水に変換したい場合は、網のメツシユ数を多
くするか網の枚数を増やすことで可能である。即ち、網
のメツシユ数と枚数は、要求される水素同位体の酸化率
と許容される圧力損失とから決定すれば良い。然して前
述の如く中間熱交換器3に入つたHeガスは冷却材二次
循環グループの冷却材であるHeガスと熱交換して温度
降下し、この温度降下したHeガスはプロア一4により
再び炉心1に送られ、Heガスと共に吸引された水は水
素同位体の分離回収部6に送られ、ここを通過する間に
水素同位体が回収される。尚、核融合炉はパルス運転に
伴う炉心ブランケツトへの熱衝撃を避ける為に、冷却材
であるHeガスを周期的にバイパス管5を通して炉心1
を迂回する。
On the other hand, if you want to increase the oxidation rate of hydrogen isotopes, in other words, if you want to convert them into water even more, you can do this by increasing the number of meshes or the number of meshes. That is, the number of meshes and the number of meshes may be determined based on the required oxidation rate of the hydrogen isotope and the allowable pressure loss. However, as mentioned above, the He gas that has entered the intermediate heat exchanger 3 exchanges heat with the He gas, which is the coolant of the secondary coolant circulation group, and its temperature is lowered. 1 and sucked together with the He gas, the water is sent to a hydrogen isotope separation and recovery section 6, where hydrogen isotopes are recovered while passing therethrough. In addition, in a fusion reactor, in order to avoid thermal shock to the core blanket due to pulse operation, He gas, which is a coolant, is periodically passed through a bypass pipe 5 to the core 1.
bypass.

この場合バイパス管5を通るHeガス中には、バイパス
管5の途中に接続した酸素供給系8″より酸素が注入さ
れ、Heガス中の水素同位体と共にバイパス管5内を流
れ、蓄熱器2に入る。蓄熱器2を含む配管7の内面には
酸化触媒がコ一テイング又は酸化触媒網が張設されてい
るので、前述の如く蓄熱器2及び配管7を通過する間に
Heガス中の水素同位体と酸素とが酸化触媒のコーテイ
ング又は網の触媒作用により反応して水に変換され、次
第に配管7内の水素同位体ガス分圧が低減し、配管7か
らの水素同位体の透過量が減少する。本発明による水素
同位体の透過量減少装置の上記実施例は、冷却材一次循
環ループの炉心1の出口から蓄熱器2を含む中間熱交換
器3の入口までの間に設けた場合であるが、Heガス中
の水素同位体を酸化する為の白金、パラジウム等の酸化
触媒は、第2図に示す如く冷却材一次循環ループ全体に
設けても良いものであり、また第3図に示す如く冷却材
一次循環ループのみならず冷却材二次循環ループにおけ
る一次中間熱交換器3の出口から蒸気発生器9の入口に
至る配管7″にも設け、その配管7″の一次中間熱交換
器3の出口附近に酸素供給系8″″を接続しても良いも
のである。
In this case, oxygen is injected into the He gas passing through the bypass pipe 5 from the oxygen supply system 8'' connected midway through the bypass pipe 5, flows through the bypass pipe 5 together with hydrogen isotopes in the He gas, and flows into the heat storage device 2. Since an oxidation catalyst is coated or an oxidation catalyst network is installed on the inner surface of the pipe 7 containing the heat storage device 2, the He gas in the He gas passes through the heat storage device 2 and the pipe 7 as described above. The hydrogen isotope and oxygen react with each other through the catalytic action of the oxidation catalyst coating or network and are converted into water, gradually reducing the partial pressure of the hydrogen isotope gas in the pipe 7 and reducing the amount of hydrogen isotope permeated from the pipe 7. The above embodiment of the hydrogen isotope permeation amount reduction device according to the present invention is provided between the outlet of the core 1 of the primary coolant circulation loop and the inlet of the intermediate heat exchanger 3 including the heat storage device 2. However, an oxidation catalyst such as platinum or palladium for oxidizing hydrogen isotopes in He gas may be provided in the entire primary coolant circulation loop as shown in Figure 2, or in the third As shown in the figure, it is installed not only in the primary coolant circulation loop but also in the piping 7'' from the outlet of the primary intermediate heat exchanger 3 to the inlet of the steam generator 9 in the secondary coolant circulation loop. An oxygen supply system 8'' may be connected near the outlet of the heat exchanger 3.

このようにすると第2図の例にあつては、中間熱交換器
3以降もHeガス中の水素同位体を水に変換することが
できるので、水素同位体の透過は極めて僅かとなり、し
かも水素同位体の分離回収量を増加することができ、ま
た第3図の例にあつては、中間熱交換器3から透過して
冷却材二次循環ループの配管7″を流れるHeガス中に
流出した僅かな水素同位体を水に変換して配管7″から
の透過を防止して安全を図ることができる。さらに本発
明による水素同位体の透過量減少装置の第1図に示す実
施例に於いては、蓄熱器2を含む配管7の内面に白金、
パラジウム等の酸化触媒をコーテイングするか又はその
酸化触媒よりなる網を張設するだけでも充分効果がある
が、要求される水素同位体の酸化率が非常に高く、許容
される圧力損失が小さい場合には、前記酸化触媒をコー
テイングすると共に酸化触媒網を張設すると良い。
In this way, in the example shown in Figure 2, hydrogen isotopes in the He gas can be converted to water even after the intermediate heat exchanger 3, so the permeation of hydrogen isotopes is extremely small, and hydrogen It is possible to increase the amount of isotope separation and recovery, and in the example shown in Fig. 3, it permeates through the intermediate heat exchanger 3 and flows into the He gas flowing through the pipe 7'' of the secondary coolant circulation loop. Safety can be ensured by converting the small amount of hydrogen isotope produced into water and preventing it from permeating through the pipe 7''. Furthermore, in the embodiment of the hydrogen isotope permeation amount reducing device according to the present invention shown in FIG.
Coating with an oxidation catalyst such as palladium or installing a net made of the oxidation catalyst is sufficient, but in cases where the required oxidation rate of hydrogen isotope is extremely high and the allowable pressure drop is small. In this case, it is preferable to coat the oxidation catalyst and provide an oxidation catalyst network.

以上詳述した通り本発明による水素同位体の透過量減少
装置によれば、少くとも冷却材一次循環ループの炉心出
口から蓄熱器を含む中間熱交換器入口に至る配管を流れ
るHeガス中に存在する水素同位体が酸化されて次第に
水に変換されるので、前記配管内の水素同位体ガス分圧
が低減され、配管から水素同位体の透過量を減少できて
、格納容器内への水素同位体の流出を許容値以下に押え
ることができて安全である。
As detailed above, according to the hydrogen isotope permeation amount reduction device according to the present invention, He gas exists at least in the piping from the core outlet of the coolant primary circulation loop to the intermediate heat exchanger inlet including the regenerator. Since the hydrogen isotope that is present in the pipe is oxidized and gradually converted to water, the partial pressure of the hydrogen isotope gas in the pipe is reduced, and the amount of hydrogen isotope that permeates from the pipe can be reduced. It is safe because the outflow of the body can be kept below the allowable value.

また前記配管を通つて中間熱交換器に入つたHeガス中
に存在する水素同位体はその量が少ないので、水素同位
体ガス分圧は極めて低く、中間熱交換器の伝熱管を透過
して冷却材二次循環ループ側に流出する水素同位体の量
は許容値以下に押えることができて安全である。従つて
従来のように格納容器を拡大する必要がなく、ガス冷却
型原子炉及び核融合炉プラントの縮小を図ることができ
て設置費用を低減できる。また本発明の装置は前述の如
く配管を流れるHeガス中の水素同位体を水に変換する
のであるから透過によつて失われる水素同位体の量が少
なく、従つて水素同位体分離回収部に送られた水から分
離回収される水素同位体の量が多いので、特にトリチウ
ムの場合は再び核燃料として使用できるので、その分離
回収量の増大は資源再利用に貢献するばかりではなく、
核融合炉の運転費つまり燃料費を低減できるなどの効果
がある。
In addition, since the amount of hydrogen isotopes present in the He gas that entered the intermediate heat exchanger through the pipe is small, the hydrogen isotope gas partial pressure is extremely low, and the hydrogen isotope gas that passes through the heat exchanger tubes of the intermediate heat exchanger is The amount of hydrogen isotopes flowing out into the secondary coolant circulation loop can be kept below the permissible value and is therefore safe. Therefore, there is no need to expand the containment vessel as in the past, and it is possible to downsize the gas-cooled nuclear reactor and nuclear fusion reactor plant, thereby reducing installation costs. Furthermore, since the device of the present invention converts hydrogen isotopes in the He gas flowing through the piping into water as described above, the amount of hydrogen isotopes lost through permeation is small, and therefore the amount of hydrogen isotopes lost in the hydrogen isotope separation and recovery section is small. Since the amount of hydrogen isotopes that can be separated and recovered from the sent water is large, especially in the case of tritium, it can be used again as nuclear fuel, so increasing the amount of separated and recovered not only contributes to resource reuse, but also
This has the effect of reducing the operating cost, or fuel cost, of a nuclear fusion reactor.

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

第1図は本発明による水素同位体の透過量減少装置を備
えた核融合炉の冷却材一次循環ループの概略図、第2図
は第1図の変更例を示す冷却材一次循環ループの概略図
、第3図は本発明装置を備えた核融合炉の冷却材一次循
環ループ及び冷却材二次循環ループの概略図である。 1・・・・・・炉心、2・・・・・・蓄熱器、3・・・
・・・中間熱交換器、4,4″・・・・・・プロア一、
5・・・・・・バイパス管、6,6″・・・・・・水素
同位体の分離回収部、7,7″・・・・・・配管、8,
8″,8″″・・・・・・酸素供給系、9・・・・・・
蒸気発生器。
Fig. 1 is a schematic diagram of the primary coolant circulation loop of a fusion reactor equipped with a hydrogen isotope permeation amount reduction device according to the present invention, and Fig. 2 is a schematic diagram of the primary coolant circulation loop showing a modification of Fig. 1. 3 are schematic diagrams of a primary coolant circulation loop and a secondary coolant circulation loop of a fusion reactor equipped with a device of the present invention. 1...Reactor core, 2...Regenerator, 3...
...Intermediate heat exchanger, 4,4''...Proa 1,
5...Bypass pipe, 6,6''...Hydrogen isotope separation and recovery section, 7,7''...Piping, 8,
8″, 8″″...Oxygen supply system, 9...
steam generator.

Claims (1)

【特許請求の範囲】[Claims] 1 ガス冷却型原子炉及び核融合炉の配管系に於いて、
少くとも冷却材一次循環ループの炉心出口から蓄熱器を
含む中間熱交換器入口に至る配管の内面に、白金、パラ
ジウム等の酸化触媒をコーティングするか又は前記酸化
触媒の網を張設すると共に、その配管の炉心出口附近及
び炉心を迂回するバイパス管の途中に夫々酸素供給系を
接続して成るガス冷却型原子炉及び核融合炉の配管系に
於ける水素同位体の透過量減少装置。
1. In the piping systems of gas-cooled nuclear reactors and nuclear fusion reactors,
Coating at least an oxidation catalyst such as platinum or palladium on the inner surface of the piping from the core outlet of the coolant primary circulation loop to the inlet of the intermediate heat exchanger including the heat storage device, or extending a network of the oxidation catalyst, A device for reducing the permeation amount of hydrogen isotopes in the piping systems of gas-cooled nuclear reactors and nuclear fusion reactors, which comprises an oxygen supply system connected to the piping near the reactor core exit and in the middle of a bypass pipe that bypasses the reactor core.
JP53009098A 1978-01-30 1978-01-30 Device for reducing hydrogen isotope permeation in piping systems of gas-cooled nuclear reactors and fusion reactors Expired JPS5953518B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP53009098A JPS5953518B2 (en) 1978-01-30 1978-01-30 Device for reducing hydrogen isotope permeation in piping systems of gas-cooled nuclear reactors and fusion reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP53009098A JPS5953518B2 (en) 1978-01-30 1978-01-30 Device for reducing hydrogen isotope permeation in piping systems of gas-cooled nuclear reactors and fusion reactors

Publications (2)

Publication Number Publication Date
JPS54102500A JPS54102500A (en) 1979-08-11
JPS5953518B2 true JPS5953518B2 (en) 1984-12-25

Family

ID=11711135

Family Applications (1)

Application Number Title Priority Date Filing Date
JP53009098A Expired JPS5953518B2 (en) 1978-01-30 1978-01-30 Device for reducing hydrogen isotope permeation in piping systems of gas-cooled nuclear reactors and fusion reactors

Country Status (1)

Country Link
JP (1) JPS5953518B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106586961A (en) * 2016-12-13 2017-04-26 中国工程物理研究院材料研究所 Tritiated water preparation apparatus and method

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57128881A (en) * 1981-02-04 1982-08-10 Hitachi Ltd Vacuum exhauster for nuclear fusion reactor
JP7591993B2 (en) * 2021-07-30 2024-11-29 三菱重工業株式会社 Heat supply system and heat supply method
CN116913558B (en) * 2023-07-06 2025-03-04 中国核电工程有限公司 A combined system of gas-cooled reactor and fusion reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106586961A (en) * 2016-12-13 2017-04-26 中国工程物理研究院材料研究所 Tritiated water preparation apparatus and method

Also Published As

Publication number Publication date
JPS54102500A (en) 1979-08-11

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