JPS58160895A - Device for capturing radioactive corrosion product - Google Patents
Device for capturing radioactive corrosion productInfo
- Publication number
- JPS58160895A JPS58160895A JP57042098A JP4209882A JPS58160895A JP S58160895 A JPS58160895 A JP S58160895A JP 57042098 A JP57042098 A JP 57042098A JP 4209882 A JP4209882 A JP 4209882A JP S58160895 A JPS58160895 A JP S58160895A
- Authority
- JP
- Japan
- Prior art keywords
- coolant
- capture
- radioactive corrosion
- flow
- corrosion products
- 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.)
- Granted
Links
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Manufacture And Refinement Of Metals (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は、原子炉の冷却材に含まれる放射性腐食生成物
を捕獲する放射性腐食生成物捕獲装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a radioactive corrosion product capture device for capturing radioactive corrosion products contained in the coolant of a nuclear reactor.
高速増殖炉においては、冷却材として、一般に液体ナト
リウムで代表されるアルカリ土類金属が用いられている
。そして、このような・液体金属冷却材は、原子炉容器
内の炉心で加熱された後、容器外に設けられた1次冷却
系へと導びかれ、再び原子炉容器内へと戻され、循環す
る。In fast breeder reactors, alkaline earth metals represented by liquid sodium are generally used as coolants. After being heated in the reactor core inside the reactor vessel, such liquid metal coolant is guided to the primary cooling system provided outside the vessel, and then returned to the reactor vessel. circulate.
ところで、高速増殖炉の場合、核・給料要素の被覆管や
炉心構造物は、通常、ステンレス鋼で構成されるが、こ
れ等の構成材料が中性子の照射をうけると、上記構成材
料に含まれている鉄、コバルト等が核反応(を、起し、
マンがンー54゜コパル)−60、コ・ぐルトー58等
の放射性核種が多量に生成される。この構成材料は冷却
材として用いられている前述のアルカリ土類金属により
腐食され冷却材中へ放出される。このとき前述の放射性
核種も冷却材中へ放出され、いわゆる放射性腐食生成物
が冷却材へ混入することになる。By the way, in the case of fast breeder reactors, the cladding tubes and core structures of the nuclear and payload elements are usually made of stainless steel, but when these constituent materials are irradiated with neutrons, they are Iron, cobalt, etc. that are present cause a nuclear reaction (,
Large amounts of radionuclides such as Mann-54° Copal)-60 and Co-Gourteau-58 are produced. This material is corroded by the aforementioned alkaline earth metal used as a coolant and is released into the coolant. At this time, the aforementioned radionuclides are also released into the coolant, and so-called radioactive corrosion products are mixed into the coolant.
冷却材へ混入した放射性腐食生成物は冷却材の流れに従
って、1次冷却系へと運ばれ、中間熱交換器等の1次冷
却系機器配管の噸面等に沈着する。このように、1次冷
却系の壁面等に沈着した放射性腐食生成物の放射能はポ
ンプ、熱交換器、・々ルデ、fi量計等の機器やこれ等
の機器に接続され九配管の保守、補修等の作業・に障害
を与える。特に、マンがノー54.コバルト−60、コ
・肴ルトー58等は生成量も多く、半減期も長いためK
その影響が大きい。The radioactive corrosion products mixed into the coolant are carried to the primary cooling system according to the flow of the coolant, and are deposited on the surfaces of the pipes of primary cooling system equipment such as intermediate heat exchangers. In this way, the radioactivity of the radioactive corrosion products deposited on the walls of the primary cooling system is removed from equipment such as pumps, heat exchangers, heat exchangers, and fi meter, and maintenance of nine piping systems connected to these equipments. , causing trouble to repair work, etc. In particular, Mann is No. 54. Cobalt-60, Co-Harto-58, etc. are produced in large amounts and have long half-lives, so they are
That has a big impact.
そこで、このような不具合を解消するために、最近では
、二、ケルが高温の液体金属ナトリウム中でマンがy−
54,コ・寸ルト−60%O放射性核種を効率よく捕獲
する性質を有していることを利用し九放射性腐食生成物
捕曙装置を原子炉容器内に設置することが考えられてい
る。Therefore, in order to solve this problem, recently, two Kels have been working on y-
It is being considered that a radioactive corrosion product trapping device can be installed inside the reactor vessel by taking advantage of its ability to efficiently capture 54, 60% O radionuclides.
この放射性腐食生成物捕獲装置は、炉心の冷却材出口に
対向させて、つまり炉心上方に前記二、ケル等の捕獲材
を収容した要素を複数配置し、炉心から流出した冷却材
を上記i種材に直接接触させることKよって、放射性核
種を捕獲するようにしている。This radioactive corrosion product capture device has a plurality of elements containing capture materials such as the above-mentioned 2, Kel, etc. arranged opposite to the coolant outlet of the reactor core, that is, above the reactor core, and collects the above-mentioned type i type of coolant flowing out from the reactor. Radioactive nuclides are captured by direct contact with the material.
前記のような姿蓋にあって、効率よく放射性腐食生成物
の核種を禰1するには、捕獲材と冷却材との接触面積を
ある1度以上大きくするとともにすべての冷却材を上記
捕獲材に均一に接触させることが必要である。In order to efficiently remove the nuclides of radioactive corrosion products using the above-mentioned lid, the contact area between the capture material and the coolant must be increased by at least a certain degree, and all of the coolant must be removed from the capture material. It is necessary to make uniform contact with the
しかしながら、冷却材が捕獲材間を流れる場合には、冷
却材の粘性作用により、捕獲材の表面近傍に層流をなす
、いわゆる境界層が形成される。この境界層を形成して
いる冷却材と境界層の外側を流れる冷却材との間の位置
交換は少い、したがって、捕獲材間に形成された流路の
中央部を流れる冷却材が捕獲材に接触する確率は小さい
、この九め、中央部を流れる冷却材中の放射性腐食生成
物は、専ら前記境界層を拡散して上記捕獲材KrI&着
されることになるが、上記境界層中での放射性腐食生成
物の拡散速度は非常に遅く、このため、捕獲効率が低く
、結局、装置全体の効率が低いという問題がめった。However, when the coolant flows between the capture materials, a so-called boundary layer, which forms a laminar flow near the surface of the capture materials, is formed due to the viscous effect of the coolant. There is little exchange of position between the coolant forming this boundary layer and the coolant flowing outside the boundary layer. Therefore, the coolant flowing in the center of the flow path formed between the captured materials The radioactive corrosion products in the coolant flowing in the central part are only likely to come into contact with KrI, and the radioactive corrosion products in the coolant flowing through the center will diffuse through the boundary layer and be deposited on the trapping material KrI. The diffusion rate of radioactive corrosion products is very slow, which often leads to low capture efficiency and ultimately low overall efficiency of the device.
本発明は、このような事情Ksみてなされた 1もの
で、その目的とするところは、簡単な構成であるにもか
かわらず、冷却材を効率よく捕獲体く接触させることが
でき、もって、捕獲効率の向上化を図れる放射性腐食生
成物捕matを提供することKある。The present invention was developed in view of the above circumstances, and its purpose is to efficiently bring the coolant into contact with the captured material, despite its simple structure, and thereby to reduce the captured material. It is an object of the present invention to provide a radioactive corrosion product trapping mat capable of improving efficiency.
本発明の放射性腐食生成物捕1装置は、放射性腐食生成
物の混入した原子炉冷却材の流路内にその表面に沿って
移動する上記冷却材の後流域を積極的に乱流化させる一
率表面を有した放射性核種捕獲体を複数配置してなるこ
とを特徴としている。The radioactive corrosion product trapping device of the present invention is a device that actively creates turbulence in the trailing region of the coolant that moves along the surface of the reactor coolant mixed with radioactive corrosion products in the flow path. It is characterized by having a plurality of radionuclide capture bodies each having a transparent surface.
一般に、流路内に置かれた物体の周囲を流れる粘性流体
の流れの形態は、ナビア・ストークスの解によって与え
られるが、この解は流体の動粘度r、流体の流速V、物
体の代表寸法(球の場合には直径)Lによって次式のよ
うに定義されるレイノルズ数R・の値により大きく影響
される。Generally, the flow form of a viscous fluid that flows around an object placed in a flow channel is given by the Navier-Stokes solution, and this solution consists of the kinematic viscosity r of the fluid, the flow velocity V of the fluid, and the representative dimensions of the object. (diameter in the case of a sphere) L is greatly influenced by the value of the Reynolds number R. defined as the following equation.
L R@W 。L R@W.
すなわち、上記レイノルズ数8・がある程度以上又は乱
流と言う是非定常流が形成されるととKなる。That is, when the above-mentioned Reynolds number 8. is above a certain level or when a steady flow called turbulent flow is formed, it becomes K.
このように、非定常流が形成されると、物体の下流側表
面忙形成される境界層が乱され、この境界層が薄くなっ
たり、剥離したりする6本発明はこのような現象を利用
したもので、冷却材の流路内にその後流域を積極的にI
L鷹化させる一率表面をもった捕獲体を複数設けるよう
にしているのである。In this way, when an unsteady flow is formed, the boundary layer formed on the downstream surface of the object is disturbed, and this boundary layer becomes thin or peels off.6 The present invention takes advantage of this phenomenon. After that, the flow area of the coolant is actively injected into the flow path of the coolant.
A plurality of capture bodies with a uniform surface for L-hawking are provided.
したがって、冷却材が捕獲体に接触する確率會大きくす
ることができ、しかも境界層の薄膜化によって中央部を
流れる冷却材中の放射性腐食生成物の核種が上記境界層
を拡散して上記捕獲体に到達するまでの時間を噌縮する
ことができ、それ故、上記中央部を流れる冷却材中の放
射性腐食生成物の核種を効率よく上記複数の捕獲体にて
捕獲させることができ、結局、冷却材中に1大した放射
性腐食生成物を多睦に捕獲することかできる、し九がっ
て、この装置を原子炉容器の冷却材出口に設けておけば
、放射性1食生成物が中間熱交換器等の機器まで流れる
のを防止できるので、この系の保守、補修等の作業の容
易化に寄与できる。Therefore, the probability that the coolant comes into contact with the capture body can be increased, and the thinning of the boundary layer allows the nuclides of the radioactive corrosion products in the coolant flowing in the center to diffuse through the boundary layer and the capture body. Therefore, the nuclides of the radioactive corrosion products in the coolant flowing through the central part can be efficiently captured by the plurality of capture bodies, and in the end, It is possible to capture a large amount of radioactive corrosion products in the coolant, and if this device is installed at the coolant outlet of the reactor vessel, the radioactive corrosion products will be captured in the middle. Since it can be prevented from flowing to equipment such as heat exchangers, it can contribute to facilitating maintenance and repair work of this system.
11i11図は本発明の一実施例に係る放射性腐食生成
物捕獲装置の概略構成を示す縦断面図であり、この放射
性腐金生成物捕獲装置は、主に、内部に冷却材1が通流
する円筒体2と、この円筒体2の内部で上記冷却材1の
流れ方向を基準として上流部に配置された第1の捕獲体
Sと、この第1の捕獲体3よシ下流部に配置された第2
の捕獲体4と、この第2の捕獲体4よ)さらに下流部に
配置された第3の捕獲体5とで構成されている。FIG. 11i11 is a vertical cross-sectional view showing a schematic configuration of a radioactive corrosion product capture device according to an embodiment of the present invention. A cylindrical body 2, a first capture body S disposed upstream within the cylindrical body 2 with respect to the flow direction of the coolant 1, and a first capture body S disposed downstream of the first capture body 3. second
A third capture body 5 is disposed further downstream of the second capture body 4.
前記円筒体2はステンレス鋼で形成されており、その両
端開口6には冷却材1t−案内する配管rが接続されて
いる。The cylindrical body 2 is made of stainless steel, and openings 6 at both ends thereof are connected to piping r for guiding the coolant 1t.
前記第1の捕獲体3.第2の捕獲体4および第3の捕獲
体5はすべて同一構成のもので各捕1体は、前記円筒体
2の軸心線上に配置されたステンレス鋼製の球8と、こ
の球8を含む上記−心alKm直な面内で、第2図に示
すように、上記域1の18Hに放射状に配置された上記
域8より小径のステンレス鋼製の4個の球9と、これら
の球8.9を上記円筒体2のm*内面に固定支持する丸
めの支持体10とで構成されている。Said first capture body 3. The second capture body 4 and the third capture body 5 are all of the same configuration, and each capture body includes a stainless steel ball 8 arranged on the axis of the cylindrical body 2, and a stainless steel ball 8 disposed on the axis of the cylindrical body 2. In the plane perpendicular to the above-mentioned center alKm, as shown in FIG. 8.9 and a round support 10 fixedly supported on the m* inner surface of the cylindrical body 2.
なお、上記第1〜第3の捕獲体3.4.5が設置されて
いる部分の冷却材1の流路の最小断面積、すなわち、第
2図における円筒体2内の球8.#と支持体10を除い
た関[11部分の総面積は、冷却材1が通流する前記配
管1の断面積より小さくなるように上記域8.9および
円筒体2の径が設定されている。Note that the minimum cross-sectional area of the flow path of the coolant 1 in the portion where the first to third capture bodies 3.4.5 are installed, that is, the sphere 8. in the cylindrical body 2 in FIG. The diameters of the area 8.9 and the cylindrical body 2 are set so that the total area of the section 11 excluding # and the support 10 is smaller than the cross-sectional area of the pipe 1 through which the coolant 1 flows. There is.
このような構成であると、原子炉運転時には、冷却材1
は第1図中の矢印で示すように第1〜 11第3の捕
獲体!、4.5内の間tM11を流れる。With such a configuration, during reactor operation, the coolant 1
As shown by the arrows in Figure 1, the first to eleventh captured bodies are the third! , 4.5.
この場合、上記捕獲体を構成する球8.9の表面には前
述したように層流による境界層が形成されるが、この流
路系におけるレイノルズ数が十分大きいと(R・〉2)
、上記境界層は流れ方向の最大幅位置にて上記域8.9
の表面から離脱し、その結果、上記域8.9の後流域に
うす流又は乱流が発生する。したがりて、上記冷却材1
中に混入した放射性腐食生成物の核種は、放射性核種捕
獲材としてのステンレス鋼製の球8.9にて効率よく捕
獲され、結局、放射性腐食生成物が中間熱交換器等の機
器まで流れるのを防止できるので、この系の保守、補修
等の作業の容易化に寄与できる。In this case, a boundary layer due to laminar flow is formed on the surface of the sphere 8.9 constituting the capture body as described above, but if the Reynolds number in this flow path system is sufficiently large (R・〉2)
, the boundary layer has the above area 8.9 at the maximum width position in the flow direction.
as a result of which a thin or turbulent flow occurs in the downstream region of the region 8.9. Therefore, the above coolant 1
The nuclides of the radioactive corrosion products mixed in are efficiently captured by the stainless steel balls 8.9 that serve as radionuclide capture materials, and the radioactive corrosion products eventually flow to equipment such as intermediate heat exchangers. This can contribute to facilitating maintenance, repair, etc. of this system.
特に、実施例では、冷却材1の流路である円筒体2の断
面全体に捕獲材としての5個の球89を分布配置してい
るので、上記域8.9によって形成されるうす流又は乱
流は上記円筒体2の断面全体に分布され、結局、冷却材
1の流れの全断面においてよシ均一な捕獲効果を得るこ
とができる。In particular, in the embodiment, five balls 89 as trapping materials are distributed over the entire cross section of the cylindrical body 2, which is the flow path for the coolant 1, so that the thin flow formed by the area 8.9 or The turbulent flow is distributed over the entire cross section of the cylinder 2, resulting in a very uniform trapping effect over the entire flow cross section of the coolant 1.
また、捕獲体が設置されている部分における冷却材10
通通魔間積(例えば、第1図のA−?
ム断向)を配管1の断面積よシ小さくしているので、上
記捕獲体が設着されている部分の冷却材1の流速が増大
し、前述のレイノズル数R・が増大するので、結局、冷
却材1のうす流又は乱流がよシ発生しやすくなり、前述
の捕獲効果をより向上させることができる。In addition, the coolant 10 in the part where the capture body is installed
Since the cross-sectional area of the pipe 1 is made smaller than the cross-sectional area of the pipe 1, the flow velocity of the coolant 1 increases in the part where the above-mentioned capture body is installed. However, since the above-mentioned Ray nozzle number R. increases, the thin flow or turbulent flow of the coolant 1 becomes more likely to occur, and the above-mentioned trapping effect can be further improved.
なお、本発明は上述した実施例に限定される−のではな
い、実施例では捕獲材としてステンレス鋼を用いたが、
二、ケル、又はニッケル合金であってもよい、また、捕
獲材の形状も球でなくて、楕円体又は他の形状であって
もよい。It should be noted that the present invention is not limited to the embodiments described above; in the embodiments, stainless steel was used as the capture material;
2. It may be made of Kel or a nickel alloy. Also, the shape of the capture material may not be spherical, but may be an ellipsoid or other shape.
さらに、1捕獲体を構成する球の数および冷却材の流れ
方向に分布配置する捕獲体の数も特に限定されるもので
はない。Furthermore, the number of balls constituting one catcher and the number of catchers distributed in the flow direction of the coolant are not particularly limited.
第1因は本発明の一実施例に係る放射性腐食生成物捕獲
装置の概略構成を示す縦断面図、第2図は第1図のA−
A@に沿って切断し矢印方向に見え断面図である。
第1図
第2図
1
ソ −
1The first factor is a vertical cross-sectional view showing the schematic configuration of a radioactive corrosion product capture device according to an embodiment of the present invention, and FIG.
It is a sectional view taken along A@ and viewed in the direction of the arrow. Figure 1 Figure 2 1 So-1
Claims (1)
路と、との流路内に配置され前記放射性腐食生成物を吸
着捕獲する複数の捕獲体とを具備し、上記捕獲体は、こ
の捕獲体の表i[K沿って移動する前記冷却材の流れの
後流域を積極的に乱流化させる曲率表面に形成されてな
ることを特徴とする放射性腐食生成物捕獲装置。a channel for guiding reactor coolant mixed with radioactive corrosion products; and a plurality of capture bodies arranged in the flow channels to adsorb and capture the radioactive corrosion products; A radioactive corrosion product trapping device, characterized in that the trapping body is formed with a curved surface that actively creates turbulence in the trailing region of the flow of the coolant moving along the surface i[K.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57042098A JPS58160895A (en) | 1982-03-17 | 1982-03-17 | Device for capturing radioactive corrosion product |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP57042098A JPS58160895A (en) | 1982-03-17 | 1982-03-17 | Device for capturing radioactive corrosion product |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS58160895A true JPS58160895A (en) | 1983-09-24 |
JPS645673B2 JPS645673B2 (en) | 1989-01-31 |
Family
ID=12626512
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP57042098A Granted JPS58160895A (en) | 1982-03-17 | 1982-03-17 | Device for capturing radioactive corrosion product |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS58160895A (en) |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5390600A (en) * | 1977-01-18 | 1978-08-09 | Us Government | Method of controlling deposition of radioactive nuclide |
JPS5419269A (en) * | 1977-07-08 | 1979-02-13 | Commissariat Energie Atomique | Magnetic filter |
JPS564099A (en) * | 1979-06-25 | 1981-01-16 | Tokyo Shibaura Electric Co | Device for removing radioactive nuclide |
-
1982
- 1982-03-17 JP JP57042098A patent/JPS58160895A/en active Granted
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5390600A (en) * | 1977-01-18 | 1978-08-09 | Us Government | Method of controlling deposition of radioactive nuclide |
JPS5419269A (en) * | 1977-07-08 | 1979-02-13 | Commissariat Energie Atomique | Magnetic filter |
JPS564099A (en) * | 1979-06-25 | 1981-01-16 | Tokyo Shibaura Electric Co | Device for removing radioactive nuclide |
Also Published As
Publication number | Publication date |
---|---|
JPS645673B2 (en) | 1989-01-31 |
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