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JPS6140958B2 - - Google Patents
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JPS6140958B2 - - Google Patents

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Publication number
JPS6140958B2
JPS6140958B2 JP55038180A JP3818080A JPS6140958B2 JP S6140958 B2 JPS6140958 B2 JP S6140958B2 JP 55038180 A JP55038180 A JP 55038180A JP 3818080 A JP3818080 A JP 3818080A JP S6140958 B2 JPS6140958 B2 JP S6140958B2
Authority
JP
Japan
Prior art keywords
magnetic
flow tube
removal device
flow
magnetic pole
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
JP55038180A
Other languages
Japanese (ja)
Other versions
JPS56135197A (en
Inventor
Hirohiko Sakai
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP3818080A priority Critical patent/JPS56135197A/en
Publication of JPS56135197A publication Critical patent/JPS56135197A/en
Publication of JPS6140958B2 publication Critical patent/JPS6140958B2/ja
Granted legal-status Critical Current

Links

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  • Water Treatment By Electricity Or Magnetism (AREA)

Description

【発明の詳細な説明】 本発明は、例えば液体ナトリウム冷却高速増殖
炉(以下FBRと称す)における一次冷却材(金
属ナトリウム)中に存在する放射性物質である、
例えば核分裂生成物(以下FPと称す)あるいは
放射性腐食生成物(以下CPと称す)などの放射
性核種を、その冷却材中から除去する放射性物質
除去装置に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention is a radioactive substance present in the primary coolant (metallic sodium) in, for example, a liquid sodium cooled fast breeder reactor (hereinafter referred to as FBR).
The present invention relates to a radioactive substance removal device that removes radionuclides such as fission products (hereinafter referred to as FP) or radioactive corrosion products (hereinafter referred to as CP) from coolant.

FBRは、その運転中に炉内の燃焼ピンが破損
すると、燃焼ピン中に生成していたFPが冷却材
中に放出される。これらの放出された放出FP
は、希ガスFP、揮発性FP、不揮発性FPの3種
に大別される。このうち希ガスFPは一部が炉心
上部プレナムからカバーガス中へ移行し、冷却材
中に残つた大部分は壊変を繰り返し、不揮発性の
FPに変化し、プラント内の配管内壁に沈着す
る。ヨウ素、テルル、セシウムなどの揮発性FP
は冷却材中に溶解してコールドトラツプに移行し
大部分が捕獲され除去される。不揮発性FPは燃
料ピンから放出されるとまもなくブラント内の配
管内壁に沈着する。一方炉心構造材、例えば燃料
被覆管(以下構造材と略記する)は、主にステン
レス鋼でできているが、炉心部における高密度な
中性子照射を受けて強く放射化する。生成する主
な核種は、Cr−51、Mn−54、Fe−59、Co−
58、Co−60などである。放射化した構造材は、
液体の高温ナトリウムによる腐食を受けCPがナ
トリウム中に放出され、プラント配管内壁に沈着
する。沈着した不揮発性FPおよびCPには長半減
期のものが多く、かつ強いγ線を放出するため、
人が一次冷却系の機器、配管に接近することは危
険となり、保守点検作業が困難となる。特に
FBRにおいては、CPの寄与の方がFPに比較して
大きい。
When a combustion pin in the furnace breaks during FBR operation, the FP generated in the combustion pin is released into the coolant. These released emission FP
is broadly classified into three types: rare gas FP, volatile FP, and nonvolatile FP. Part of the rare gas FP migrates from the upper core plenum into the cover gas, and most of the remaining gas in the coolant repeatedly disintegrates and becomes non-volatile.
It turns into FP and deposits on the inner walls of piping inside the plant. Volatile FPs such as iodine, tellurium, and cesium
is dissolved in the coolant and transferred to the cold trap, where most of it is captured and removed. Non-volatile FP is deposited on the inner wall of the pipe within the blunt shortly after being released from the fuel pin. On the other hand, reactor core structural materials, such as fuel cladding tubes (hereinafter abbreviated as structural materials), are mainly made of stainless steel, and are strongly activated when exposed to high-density neutron irradiation in the core. The main nuclides produced are Cr-51, Mn-54, Fe-59, Co-
58, Co-60, etc. The radioactive structural materials are
Corrosion caused by high-temperature liquid sodium causes CP to be released into the sodium and deposited on the inner walls of plant piping. Many of the deposited non-volatile FPs and CPs have long half-lives and emit strong γ-rays, so
It is dangerous for people to approach the equipment and piping of the primary cooling system, and maintenance and inspection work becomes difficult. especially
In FBR, the contribution of CP is larger than that of FP.

これらの沈着放射性核種のうち、CPについて
は、炉心上方にニツケルを主体としたトラツプ装
置を設置し、吸着により捕獲除去し、それ以降の
プラントへのCPの移行を減少させる方法が考案
されている。しかしこの方法では、ある一定時間
経過するとCPトラツプ装置の吸着能力が飽和に
達し、これ以上ナトリウムに浸漬していると逆に
はく離を起して一次冷却系の後方に移行する可能
性があるため、定期的に交換する必要があつた。
Among these deposited radionuclides, a method has been devised to reduce the subsequent transfer of CP to the plant by installing a trap device mainly made of nickel above the reactor core to capture and remove it through adsorption. . However, with this method, the adsorption capacity of the CP trap device reaches saturation after a certain period of time, and if it is immersed in sodium any longer, it may peel off and migrate to the rear of the primary cooling system. , it was necessary to replace it periodically.

本発明は上記の事情に基きなされたもので、強
磁性および常磁性のFPおよびCPを捕獲除去し、
かつプラントの寿命の間交換する必要のない放射
性物質の除去装置を提供することを目的としてい
る。
The present invention was made based on the above circumstances, and it captures and removes ferromagnetic and paramagnetic FPs and CPs, and
The object of the present invention is to provide a radioactive material removal device that does not require replacement during the life of the plant.

放射性物質を含む、例えば液体ナトリウムのよ
うな液体金属の流体が流通しかつ非磁性体かうな
る断面偏平の流管の上記偏平部分の短径方向にか
つ流通方向に所定の距離を有して磁場を印加する
磁場発生部と、この磁場発生部の磁極が対向する
上記流管内の一側面もしくは両側面に上記磁極の
対向する面上に突出し、かつ対向する磁極に接触
しないように設けた磁性体からなる磁極体とを具
備し、上記磁極体は上記流管内に流体の流れを妨
げないように流通方向に沿つて延在して設けるこ
とにより上記流管内に複数の勾配磁場を形成して
なる放射性物質除去装置であり、また、特に上記
磁極体を流管内に流れる流体の流通方向に沿つて
延在するような板状を呈し、かつ磁極の対向する
両側面上にくしの歯状に互い違いに接触しないよ
うに設けた放射性物質除去装置であり、さらに、
また上記勾配磁場を液体金属冷却高速増殖炉の炉
心出口配管に形成した放射性物質除去装置であ
り、さらにまた、偏平の流管の断面積を液体金属
冷却高速増殖炉の一次系主要配管の断面積と同じ
断面積に形成した放射性物質除去装置であり、配
管内に大きな勾配をもつた磁場を発生させ、強磁
性および常磁性のFPおよびCPを捕獲除去するよ
うにしたものである。
A magnetic field is applied at a predetermined distance in the direction of flow in the short axis direction of the flat section of the flow tube, which is made of a non-magnetic material and has a flat cross section, through which a fluid of liquid metal, such as liquid sodium, containing a radioactive substance flows. a magnetic field generating section that applies a magnetic field, and a magnetic body provided on one or both sides of the flow tube where the magnetic poles of the magnetic field generating section are opposed so as to protrude above the opposing surface of the magnetic poles and not to come into contact with the opposing magnetic poles. The magnetic pole body is provided to extend along the flow direction so as not to impede the flow of fluid within the flow tube, thereby forming a plurality of gradient magnetic fields within the flow tube. It is a radioactive substance removal device, and in particular, the magnetic pole body has a plate shape that extends along the flow direction of the fluid flowing in the flow tube, and the magnetic pole body has a plate shape that extends along the flow direction of the fluid flowing in the flow tube, and the magnetic pole bodies are arranged alternately in a comb-like shape on both opposing sides of the magnetic pole. It is a radioactive material removal device installed so as not to come into contact with the
In addition, it is a radioactive material removal device in which the above gradient magnetic field is formed in the core exit piping of a liquid metal cooled fast breeder reactor, and furthermore, the cross sectional area of the flat flow tube is the cross sectional area of the primary system main piping of the liquid metal cooled fast breeder reactor. This is a radioactive substance removal device formed to have the same cross-sectional area as the pipe, and generates a magnetic field with a large gradient inside the pipe to capture and remove ferromagnetic and paramagnetic FP and CP.

以下図面につき本発明の詳細を説明する。第1
図は本発明の実施例の断面図である。一次ナトリ
ウム主循環系配管と同一の配管断面積を持つ非磁
性体の長方形配管1の上下方向にくしの歯状に互
い違いに接触しないように磁性体からなる磁極板
2を冷却材3の流れの方向に設置する。配管1の
上下の両側に大きな磁極4を設け、配管が設置し
てある反対側にコイル5を巻きつける。コイル5
に電流を流すことにより、上下の磁極4は強力に
磁化される。しかもくしの歯状の磁極板2も強く
磁化されるため、上下方向の磁極板2間に大きな
磁場の勾配が生ずる。冷却材3の中を流れていた
強磁性および常磁性のFPおよびCPは強力に磁極
板2に引き寄せられ、磁極板2の上に吸引する。
磁極板2上に吸引したFP、CPは、強力な磁気力
により吸着しているため、冷却材の流れによつて
脱着することはない。また磁極板2をさらに密に
配置することにより、磁場勾配はさらに大きくす
ることができ、吸引力は増大する。
The invention will be explained in detail below with reference to the drawings. 1st
The figure is a sectional view of an embodiment of the invention. The magnetic pole plates 2 made of a magnetic material are arranged in a comb pattern in the vertical direction of a rectangular pipe 1 made of a non-magnetic material having the same cross-sectional area as the primary sodium main circulation system piping so that they do not come in contact with each other alternately. Install in the direction. Large magnetic poles 4 are provided on both the upper and lower sides of the pipe 1, and a coil 5 is wound around the opposite side where the pipe is installed. coil 5
By passing a current through, the upper and lower magnetic poles 4 are strongly magnetized. Moreover, since the comb-tooth-shaped magnetic pole plates 2 are also strongly magnetized, a large magnetic field gradient is generated between the vertical magnetic pole plates 2. The ferromagnetic and paramagnetic FP and CP flowing in the coolant 3 are strongly attracted to the magnetic pole plate 2 and attracted onto the magnetic pole plate 2.
Since the FP and CP attracted onto the magnetic pole plate 2 are attracted by strong magnetic force, they are not detached by the flow of the coolant. Further, by arranging the magnetic pole plates 2 more closely, the magnetic field gradient can be further increased, and the attractive force is increased.

上記の如く、本発明により、プラントの寿命の
間交換することなく、本装置はFP、CPのトラツ
プとして働かせることができる。しかも、冷却材
の流れに乱れを生じさせ、FP、CPの磁極板に衝
突する機会を増大させれば、捕獲除去効率はさら
に大きくなる。特にCPには強磁性のものが多い
ため、効果は絶大である。
As mentioned above, the present invention allows the device to serve as a trap for FPs and CPs without having to be replaced during the life of the plant. Furthermore, if the flow of the coolant is disturbed and the chances of it colliding with the magnetic pole plates of the FP and CP are increased, the capture and removal efficiency will be further increased. In particular, many CPs are ferromagnetic, so the effect is tremendous.

なお本発明は上記の実施例のみに限定されな
い。例えば第2図のように片側のみにくしの歯状
の磁極板2を設けてもよい。また磁極板を冷却材
の流れに平行に設置せず、第3図のように、冷却
材の流れ6に対して、磁極板2を波形に配置して
もよい。このようにすることにより、冷却材中に
存在するFP、CPの磁極板2への衝突する機会が
増加し、捕獲除去効率は増大する。
Note that the present invention is not limited to the above embodiments. For example, as shown in FIG. 2, a comb-toothed magnetic pole plate 2 may be provided only on one side. Alternatively, the magnetic pole plates 2 may be arranged in a corrugated manner with respect to the coolant flow 6, as shown in FIG. 3, instead of disposing the magnetic pole plates parallel to the flow of the coolant. By doing so, the chances of the FP and CP present in the coolant colliding with the magnetic pole plate 2 are increased, and the capture and removal efficiency is increased.

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

第1図は本発明一実施例を示す一部切断斜方
図、第2図は本発明の一実施例の冷却材配管部の
みを示した一部切断正面図、第3図は本発明の一
実施例の冷却材配管部のみを示した一部切断上面
図である。 1……長方形一次冷却系配管、2……磁極板、
3……冷却材(ナトリウム)、4……磁極、5…
…コイル、6……ナトリウムの流れ。
FIG. 1 is a partially cutaway perspective view showing one embodiment of the present invention, FIG. 2 is a partially cutaway front view showing only the coolant piping section of one embodiment of the present invention, and FIG. FIG. 2 is a partially cutaway top view showing only the coolant piping section of one embodiment. 1... Rectangular primary cooling system piping, 2... Magnetic pole plate,
3... Coolant (sodium), 4... Magnetic pole, 5...
...Coil, 6... Sodium flow.

Claims (1)

【特許請求の範囲】 1 放射性物質を含む液体金属の流体が流通しか
つ非磁性体からなる断面偏平の流管と、この流管
の前記偏平部分の短径方向にかつ流通方向に所定
距離を有して磁場を印加する磁場発生部と、この
磁場発生部の磁極が対向する前記流管内の一側面
もしくは両側面に前記磁極の対向する面上に突出
し、かつ対向する磁極に接触しないように設けた
磁性体からなる磁極体とを具備し、前記磁極体は
前記流管内に流体の流れを妨げないように流通方
向に沿つて延在して設けることにより前記流管内
に複数の勾配磁場を形成してなることを特徴とす
る放射性物質除去装置。 2 磁極体を流管内に流れる流体の流通方向に沿
つて延在するような板状を呈しかつ磁極の対向す
る両側面上にくしの歯状に互い違いに接触しない
ように設けたことを特徴とする特許請求の範囲第
1項記載の放射性物質除去装置。 3 磁極体を流管内に流れる流体の流通方向に沿
つて波形に形成した板状体としたことを特徴とす
る特許請求の範囲第1項記載の放射性物質除去装
置。 4 勾配磁場を液体金属冷却高速増殖炉の炉心出
口配管に形成したことを特徴とする特許請求の範
囲第1項記載の放射性物質除去装置。 5 偏平の流管をその断面積が液体金属冷却高速
増殖炉の一次系主要配管の断面積と同じ断面積に
形成したことを特徴とする特許請求の範囲第4項
記載の放射性物質除去装置。 6 液体金属を液体ナトリウムとしたことを特徴
とする特許請求の範囲第1項記載の放射性物質除
去装置。
[Scope of Claims] 1. A flow tube with a flat cross section made of a non-magnetic material and through which a liquid metal fluid containing a radioactive substance flows, and a predetermined distance in the short axis direction of the flat portion of the flow tube in the flow direction. a magnetic field generating section for applying a magnetic field, and a magnetic field generating section whose magnetic poles protrude onto one or both opposing sides of the flow tube so as not to come into contact with the opposing magnetic poles. A magnetic pole body made of a magnetic material is provided, and the magnetic pole body is provided so as to extend along the flow direction so as not to impede the flow of fluid within the flow tube, thereby generating a plurality of gradient magnetic fields within the flow tube. A radioactive substance removal device characterized by being formed by forming. 2. The magnetic pole bodies are plate-shaped so as to extend along the flow direction of the fluid flowing in the flow tube, and are provided on both opposing sides of the magnetic poles in a comb-like manner so as not to come into contact with each other alternately. A radioactive substance removal device according to claim 1. 3. The radioactive substance removal device according to claim 1, wherein the magnetic pole body is a plate-shaped body formed in a corrugated shape along the flow direction of the fluid flowing in the flow tube. 4. The radioactive material removal device according to claim 1, wherein a gradient magnetic field is formed in a core exit pipe of a liquid metal cooled fast breeder reactor. 5. The radioactive material removal device according to claim 4, wherein the flat flow tube is formed to have the same cross-sectional area as the cross-sectional area of the primary system main piping of a liquid metal cooled fast breeder reactor. 6. The radioactive substance removal device according to claim 1, wherein the liquid metal is liquid sodium.
JP3818080A 1980-03-27 1980-03-27 Device for removing radioactive substance Granted JPS56135197A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3818080A JPS56135197A (en) 1980-03-27 1980-03-27 Device for removing radioactive substance

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3818080A JPS56135197A (en) 1980-03-27 1980-03-27 Device for removing radioactive substance

Publications (2)

Publication Number Publication Date
JPS56135197A JPS56135197A (en) 1981-10-22
JPS6140958B2 true JPS6140958B2 (en) 1986-09-11

Family

ID=12518180

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3818080A Granted JPS56135197A (en) 1980-03-27 1980-03-27 Device for removing radioactive substance

Country Status (1)

Country Link
JP (1) JPS56135197A (en)

Also Published As

Publication number Publication date
JPS56135197A (en) 1981-10-22

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