JPS6140957B2 - - Google Patents
Info
- Publication number
- JPS6140957B2 JPS6140957B2 JP55049547A JP4954780A JPS6140957B2 JP S6140957 B2 JPS6140957 B2 JP S6140957B2 JP 55049547 A JP55049547 A JP 55049547A JP 4954780 A JP4954780 A JP 4954780A JP S6140957 B2 JPS6140957 B2 JP S6140957B2
- Authority
- JP
- Japan
- Prior art keywords
- coolant
- radioactive
- magnetic field
- flow path
- flow
- 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
Links
- 239000002826 coolant Substances 0.000 claims description 20
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims description 12
- 239000000463 material Substances 0.000 claims description 11
- 230000005291 magnetic effect Effects 0.000 claims description 10
- 239000000941 radioactive substance Substances 0.000 claims description 8
- 229910052759 nickel Inorganic materials 0.000 claims description 5
- 239000012857 radioactive material Substances 0.000 claims description 3
- 230000002285 radioactive effect Effects 0.000 description 8
- 230000007797 corrosion Effects 0.000 description 5
- 238000005260 corrosion Methods 0.000 description 5
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 3
- 238000001816 cooling Methods 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- CWYNVVGOOAEACU-UHFFFAOYSA-N Fe2+ Chemical compound [Fe+2] CWYNVVGOOAEACU-UHFFFAOYSA-N 0.000 description 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 229910000990 Ni alloy Inorganic materials 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 239000013256 coordination polymer Substances 0.000 description 1
- 230000008021 deposition Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005294 ferromagnetic effect Effects 0.000 description 1
- -1 for example Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 230000005298 paramagnetic effect Effects 0.000 description 1
- 238000007747 plating Methods 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 229910052723 transition metal Inorganic materials 0.000 description 1
- 150000003624 transition metals Chemical class 0.000 description 1
Landscapes
- Water Treatment By Electricity Or Magnetism (AREA)
Description
【発明の詳細な説明】
本発明は原子炉冷却材中の不純物を捕獲し、特
に放射性物質である放射性核種を除去することの
できる放射性物質除去装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a radioactive substance removal device capable of capturing impurities in a nuclear reactor coolant and, in particular, removing radionuclides, which are radioactive substances.
液体金属を冷却材とする高速増殖炉において、
１次冷却系機器・配管部に沈着した核分裂成生物
（以下FPと称す）あるいは放射性腐食生成物（以
下CPと称す）等の放射性生成物などの放射性物
質による放射能は、原子炉停止時に行なう点検・
保守・修理等の作業で障害となる。 In a fast breeder reactor that uses liquid metal as a coolant,
Radioactivity due to radioactive substances such as fission products (hereinafter referred to as FP) or radioactive products such as radioactive corrosion products (hereinafter referred to as CP) deposited on primary cooling system equipment and piping should be removed when the reactor is shut down. inspection·
It becomes an obstacle during maintenance, repair, etc. work.
この核分裂生成物は燃料破損によつて冷却材中
へ放出される。また放射性腐食生成物は主として
炉心構造材の放射化によつて生成され、冷却材に
よる構造材の腐食や拡散によつて冷却材中へ放出
される。冷却材中へ移行した放射性生成物は、冷
却材により輸送され１次系機器及び配管壁面に沈
着する。かような放射性核種の沈着に起因する放
射能は、ポンプ、熱交換器、バルブ、流量計等の
機器や配管の保守・点検・修理等の作業に障害を
与える。特に問題となる放射性核種は生成量が多
く半減期の長いもので、核分裂生成物としては
95Zr−95Nb、140Ba−140La等があり放射性腐食生
成物としては60Co、58Co、54Mn等がある。 The fission products are released into the coolant upon fuel failure. Furthermore, radioactive corrosion products are mainly generated by activation of core structural materials, and are released into the coolant due to corrosion and diffusion of the structural materials by the coolant. The radioactive products that have migrated into the coolant are transported by the coolant and deposited on the primary system equipment and piping walls. Radioactivity caused by the deposition of such radionuclides can impede maintenance, inspection, and repair work on equipment such as pumps, heat exchangers, valves, flow meters, and piping. The radionuclides that pose a particular problem are produced in large amounts and have long half-lives, and are considered fission products.
95 Zr- 95 Nb, 140 Ba- 140 La, etc., and radioactive corrosion products include 60 Co, 58 Co, 54 Mn, etc.
従来の放射性腐食生成物の除去装置としては、
放射性核種を沈着しやすいニツケル製のトラツプ
材を冷却材の流路、たとえば炉心出口に設置した
ものがある。 Conventional equipment for removing radioactive corrosion products includes:
Some traps are made of nickel, which tends to deposit radionuclides, and are installed in the coolant flow path, such as at the exit of the reactor core.
しかしながら、このような装置では、流路を通
る冷却材の流れが流路中心部では乱流状態である
がトラツプ材との境界付近では層流をなすいわゆ
る境界層が生じており、放射性物質を捕獲体（ト
ラツプ材）で捕護するには、この境界層を拡散す
る必要がある。ところがこの境界層の拡散速度は
非常に遅いため、その除去効率はあまり良くな
い。 However, in such devices, the flow of coolant through the channel is turbulent at the center of the channel, but a so-called boundary layer occurs near the boundary with the trap material, which is a laminar flow, which prevents radioactive materials from being absorbed. This boundary layer needs to be diffused in order to trap it with a trap material. However, since the diffusion rate of this boundary layer is very slow, its removal efficiency is not very good.
この発明は、このような事情に鑑みてなされた
もので、境界層における放射性生成物の移動速度
を速めることによつて、冷却材中の放射性生成物
の除去効率の向上を図る放射性物質除去装置を提
供することを目的とする。 This invention was made in view of these circumstances, and provides a radioactive substance removal device that aims to improve the removal efficiency of radioactive products in the coolant by increasing the movement speed of the radioactive products in the boundary layer. The purpose is to provide
以下、この発明の実施例について詳細に説明す
る。第１図は図示しない原子炉の炉心を通過した
高温冷却材たとえば液体ナトリウムＬが流通する
冷却材流路の配管１の一部を示す図である。 Examples of the present invention will be described in detail below. FIG. 1 is a diagram showing a part of a pipe 1 of a coolant flow path through which a high-temperature coolant, for example, liquid sodium L, passes through the core of a nuclear reactor (not shown).
この配管１内に、本発明による放射性物質除去
装置が設置されている。この放射性物質除去装置
は同心円上に配置した４つの捕獲体としての筒体
２，３，４，５と、これら筒体２〜５の各間に設
けられ冷却体Ｌの流路６を構成するためのスペー
サ７と、筒体２の筒内に設けた複数個の内側電磁
石８と筒体５の外側に設けた複数個の外側電磁石
９と、これら電磁石８，９が冷却体Ｌに接しない
ようにした蓋体１０とで主に構成されている。筒
体２〜５は、たとえばニツケル（Ni）製である
が、Niに限らずニツケル合金でも、またステン
レスまたは鉄などの鉄系金属の表面にニツケルメ
ツキを施したものであつても良い。すなわち表面
はトラツプ材として優れた作用を有し、かつ全体
的には磁化し易い材料である。電磁石８，９は、
一般的なもので、鉄心１１にコイル１２が巻回さ
れ、直流電流を流して筒体２，５間に冷却材流路
を挾んで互いに逆の極性を有するように配置され
構成されている。 A radioactive substance removal device according to the present invention is installed within this piping 1. This radioactive substance removal device has four cylinder bodies 2, 3, 4, and 5 as trapping bodies arranged concentrically, and a flow path 6 of a cooling body L provided between each of these cylinders 2 to 5. a plurality of inner electromagnets 8 provided in the cylinder of the cylinder 2, a plurality of outer electromagnets 9 provided outside the cylinder 5, and these electromagnets 8, 9 do not contact the cooling body L. It is mainly composed of a lid body 10 having the above-mentioned structure. The cylindrical bodies 2 to 5 are made of, for example, nickel (Ni), but are not limited to Ni, and may be made of a nickel alloy, or may be made of a ferrous metal such as stainless steel or iron with nickel plating applied to the surface. That is, the surface has an excellent effect as a trapping material, and the material as a whole is easily magnetized. Electromagnets 8 and 9 are
This is a general type, in which a coil 12 is wound around an iron core 11, and a direct current is passed through the cylinder bodies 2 and 5, with a coolant flow path sandwiched therebetween, and the coils 12 are arranged so as to have opposite polarities.
筒体２〜５の冷却材Ｌと接する表面は、第２図
〜第４図に示すように、断面で見ると先端が尖鋭
な突起状の突起部を有している。この突起部は第
５図で示す曲線１３のように印加した磁界によつ
て磁力線を生じ勾配磁場が生じる。このような勾
配磁場があると、この間を流通する、たとえば
54Mn、60Co、58Co等は遷移金属で強磁性体であ
り95Zr−95Nb、140Ba−140Caは常磁性体であるた
めに、筒体すなわち捕獲体の表面に吸収されるこ
とになり、冷却材内に混在する放射性核種となつ
ている放射性物質を除去することができる。 As shown in FIGS. 2 to 4, the surfaces of the cylinders 2 to 5 that are in contact with the coolant L have protrusions with sharp tips when viewed in cross section. This protrusion generates lines of magnetic force due to the applied magnetic field as shown by curve 13 in FIG. 5, producing a gradient magnetic field. If there is such a gradient magnetic field, the magnetic field that flows between it, for example,
54 Mn, 60 Co, 58 Co, etc. are transition metals and are ferromagnetic, and 95 Zr- 95 Nb, 140 Ba- 140 Ca are paramagnetic, so they are absorbed on the surface of the cylinder, that is, the capture body. This makes it possible to remove radionuclides mixed in the coolant.
以上詳述したように、従来装置では放射性核種
が境界層を拡散して捕獲材へ達していたのに対
し、本発明の装置によれば放射性核種は境界層内
を磁場により高速で輸送されるためにその除去効
率が格段と高くなる。 As detailed above, in the conventional device, radionuclides diffuse through the boundary layer and reach the capture material, whereas in the device of the present invention, radionuclides are transported at high speed within the boundary layer by the magnetic field. Therefore, the removal efficiency becomes much higher.
尚、本発明による放射性物質除去装置を高速増
殖炉に用いて、放射性核種を含んだ冷却材を浄化
する際には、冷却材の炉心出口に本発明の装置を
設け浄化した冷却材を再び冷却系に戻すように構
成すれば良い。特に捕獲体にニツケル系の金属で
表面を構成することにより、効果的に放射性物質
を除去することができその工業的価値は大なるも
のである。 When using the radioactive material removal device according to the present invention in a fast breeder reactor to purify coolant containing radionuclides, the device of the present invention is installed at the core outlet of the coolant and the purified coolant is cooled again. It is only necessary to configure it so that it can be returned to the system. In particular, by configuring the surface of the capture body with a nickel-based metal, radioactive substances can be effectively removed, and this has great industrial value.
第１図はこの発明の一実施例を示す縦断面図、
第２図乃至第５図は本発明の実施例の一部を示す
縦断面図であり、特に第５図は外部より磁場を印
加したときの磁力線の様子を示す図である。
１……配管、２〜５……筒体（捕獲体）、８，
９……電磁石。
FIG. 1 is a longitudinal sectional view showing an embodiment of the present invention;
2 to 5 are longitudinal sectional views showing a part of an embodiment of the present invention, and in particular, FIG. 5 is a diagram showing the appearance of magnetic lines of force when a magnetic field is applied from the outside. 1...Piping, 2-5...Cylinder (capturing body), 8,
9...Electromagnet.
Claims (1)
つて少なくとも表面がニツケル系のトラツプ材か
らなりかつその表面に複数の突起部を有する磁化
し易い材料を配置し、かつ前記冷却材の流通する
流路を挾んで互いに逆極性となるように前記磁化
し易い材料に磁場を印加して前記トラツプ材の表
面に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。1. A highly magnetizable material having at least a surface made of a nickel-based trapping material and having a plurality of protrusions on the surface is disposed along the flow of the coolant containing radioactive material in the flow path, and the flow of the coolant is A radioactive substance removal apparatus characterized in that a magnetic field is applied to the easily magnetized material so as to have opposite polarities across the flow path to form a gradient magnetic field on the surface of the trap material.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4954780A JPS56147099A (en) | 1980-04-17 | 1980-04-17 | Radioactive substance removing device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4954780A JPS56147099A (en) | 1980-04-17 | 1980-04-17 | Radioactive substance removing device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56147099A JPS56147099A (en) | 1981-11-14 |
| JPS6140957B2 true JPS6140957B2 (en) | 1986-09-11 |
Family
ID=12834213
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4954780A Granted JPS56147099A (en) | 1980-04-17 | 1980-04-17 | Radioactive substance removing device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS56147099A (en) |
-
1980
- 1980-04-17 JP JP4954780A patent/JPS56147099A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56147099A (en) | 1981-11-14 |
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