JPS6071997A - Filter for treating radioactive waste liquor - Google Patents

Filter for treating radioactive waste liquor

Info

Publication number
JPS6071997A
JPS6071997A JP17917583A JP17917583A JPS6071997A JP S6071997 A JPS6071997 A JP S6071997A JP 17917583 A JP17917583 A JP 17917583A JP 17917583 A JP17917583 A JP 17917583A JP S6071997 A JPS6071997 A JP S6071997A
Authority
JP
Japan
Prior art keywords
radioactive waste
waste liquid
hollow fiber
filtration device
fiber membrane
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
JP17917583A
Other languages
Japanese (ja)
Inventor
田島 文夫
哲夫 山本
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
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP17917583A priority Critical patent/JPS6071997A/en
Publication of JPS6071997A publication Critical patent/JPS6071997A/en
Priority to US06/893,450 priority patent/US4756875A/en
Pending legal-status Critical Current

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  • Separation Using Semi-Permeable Membranes (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] 本発明は原子力発電プラントで発生する放射↑1廃液を
処理するための濾過装置に関する。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a filtration device for treating radiation↑1 waste fluid generated in a nuclear power plant.

[発明の技術的背景とその問題点] 原子力発電プラントで発生する放射性廃液の濾過装置と
しては、従来濾過助剤を用いた精密濾過装置が用いられ
ていたが、濾過助剤としてイオン交換樹脂を使用するた
め樹脂廃棄物が多量に発生し、放射性廃棄物を増加させ
ていた。
[Technical background of the invention and its problems] Conventionally, a precision filtration device using a filter aid has been used as a filtration device for radioactive waste liquid generated in nuclear power plants. Due to its use, a large amount of resin waste was generated, which led to an increase in radioactive waste.

最近このような二次廃棄物が発生せず、かつより良い処
理水質が得られる方法として限外濾過(以下tJ Fと
称する)や1μm孔径の平膜による濾過方式が採用され
ている。しかしUFは大流量の循環流量が必要なため系
統構成が複雑となり設備費が大きくなるという欠点があ
り、また1μ■孔径の平膜濾過装置は孔の目詰りが大き
く、かつ所要スペースが大きくなるという問題がある。
Recently, ultrafiltration (hereinafter referred to as tJF) and a filtration method using a flat membrane with a pore size of 1 μm have been adopted as a method that does not generate such secondary waste and provides better treated water quality. However, UF requires a large circulating flow rate, resulting in a complicated system configuration and high equipment costs.Furthermore, flat membrane filtration devices with a 1μ pore diameter have large pore clogging and require a large space. There is a problem.

すなわら、放射性廃液中の不溶解性不純物(クラッド)
の粒度分布を調べると、第1図のようになる。第1図か
ら明らかなように、該粒度分布は廃液により多少のばら
つきはあるが、主に1μmが中心で0.1μmは殆/υ
ど存在しない。
In other words, insoluble impurities (crud) in radioactive waste liquid
When examining the particle size distribution of , it becomes as shown in Figure 1. As is clear from Fig. 1, the particle size distribution varies to some extent depending on the waste liquid, but it is mainly centered around 1 μm and almost 0.1 μm/υ
It doesn't exist.

したがって、孔径が0.1μmより大幅に小さいU F
においては、孔内に殆んど固形分が進入せず、捕獲した
固形分は逆洗により除去できるので孔の目詰りは極めて
少ないという利点はあるが、UFは孔径が小さいため透
過水量が少なく、したがって所要濾過面積が大きくなり
、かつ高流量の循環流量及び高濾過圧力が必要となる。
Therefore, U F with a pore size significantly smaller than 0.1 μm
UF has the advantage that almost no solids enter the pores, and the trapped solids can be removed by backwashing, so the pores are extremely unlikely to become clogged, but UF has a small pore diameter, so the amount of water that permeates is small. Therefore, the required filtration area becomes large, and a high circulating flow rate and high filtration pressure are required.

そのため装置が複雑となり、設備費・所要スペースが大
きくなる。
Therefore, the device becomes complicated, and the equipment cost and space required increase.

一方、111m前後の孔径の平膜の濾過装置においては
、廃液中に1μ以下の固形分が多いため目詰りが多くな
り膜の交換頻度が増大する。
On the other hand, in a flat membrane filtration device with a pore diameter of about 111 m, the waste liquid contains a large amount of solids with a diameter of 1 μm or less, resulting in frequent clogging and an increase in the frequency of membrane replacement.

[発明の目的] 本発明は上記事情に鑑みてなされたもので、その目的は
、濾過面積が大きくて、しかも所要スペースが少なくて
すむ、放射性廃液を処理するための濾過装置を提供する
ことにある。
[Object of the Invention] The present invention has been made in view of the above circumstances, and its purpose is to provide a filtration device for treating radioactive waste liquid that has a large filtration area and requires less space. be.

[発明の概要] 本発明は、放射性廃液を処理するための濾過装置に係わ
るものであり、放射性廃液流入口、濾液流出口、逆洗水
排出口およびベント管を設置した容器内に、中空糸フィ
ルタを配設したことを特徴とするものである。
[Summary of the Invention] The present invention relates to a filtration device for treating radioactive waste liquid, in which a hollow fiber is installed in a container equipped with a radioactive waste liquid inlet, a filtrate outlet, a backwash water outlet, and a vent pipe. It is characterized by the provision of a filter.

[発明の実施例] 本発明の実施例を図面を参照して説明する。[Embodiments of the invention] Embodiments of the present invention will be described with reference to the drawings.

第2図は本発明の濾過装置の一実施例を示す概略図であ
る。
FIG. 2 is a schematic diagram showing an embodiment of the filtration device of the present invention.

第2図に示すように容器1には処理すべき放射性廃液を
導入する放射性廃液流入口3.ill液出口5、逆洗水
出口6.ペン1〜管7が設置されており、中空糸膜4の
モジュール2が複数個吊り下げられている。
As shown in FIG. 2, the container 1 has a radioactive waste liquid inlet 3 which introduces the radioactive waste liquid to be treated. Ill liquid outlet 5, backwash water outlet 6. Pens 1 to tubes 7 are installed, and a plurality of modules 2 of hollow fiber membranes 4 are suspended.

放射性廃液は廃液流入[13より流入し、中空糸膜4を
介して濾過され、中空糸膜内を通って濾液出口5より排
出される。濾過処理がある程度進行すると中空糸膜に捕
獲した固形分がたまるので、廃液流入1]3とi11′
m出口5との間に差圧が生ずる。
The radioactive waste liquid flows in from the waste liquid inflow [13, is filtered through the hollow fiber membrane 4, passes through the hollow fiber membrane, and is discharged from the filtrate outlet 5. When the filtration process progresses to a certain extent, the solid content captured in the hollow fiber membrane accumulates, so the waste liquid inflows 1]3 and i11'
A differential pressure is generated between the outlet 5 and the outlet 5.

その差圧が一定値に達したら逆洗を行って、洗浄廃液を
逆洗水出口6より排出する。胴部に設置したベント管7
は水扱きと空気抜きのためのものである。中空糸膜はポ
リエチレン等の多孔質樹脂で形成されている。
When the differential pressure reaches a certain value, backwashing is performed and the washing waste liquid is discharged from the backwash water outlet 6. Vent pipe 7 installed in the body
is for water handling and air removal. The hollow fiber membrane is made of porous resin such as polyethylene.

本実施例においては、中空糸膜として孔径0.1μmの
ものと孔径的1flIIlのものとを使用し、それぞれ
について逆洗回数と差圧変化の関係を調べた。その結宋
を第3図および第4図に示す。
In this example, hollow fiber membranes with a pore diameter of 0.1 μm and a pore diameter of 1 flIIl were used, and the relationship between the number of backwashing cycles and the change in differential pressure was investigated for each. Its conclusion is shown in Figures 3 and 4.

第3図は孔径的1μmの中空糸膜を使用した場合の差圧
変化を示すグラフであり、第4図は孔径的0.1μ川の
中空糸膜を使用した場合のそれである。これらのグラフ
より、孔径1μmの場合は逆洗後の差圧の上昇が激しい
が、孔径0.1μmの場合はそれが少ないことがわかる
。このことは、孔径1μmでは目詰りが生じやすいが、
0.1μmでは目詰りが少なく、0.1μmの孔径の中
空糸膜を使用した時に、放射性廃液濾過処理をより効果
的に行うことができることを示している。
FIG. 3 is a graph showing the change in differential pressure when a hollow fiber membrane with a pore diameter of 1 μm is used, and FIG. 4 is a graph showing the change in differential pressure when a hollow fiber membrane with a pore diameter of 0.1 μm is used. From these graphs, it can be seen that when the pore diameter is 1 μm, the differential pressure after backwashing increases sharply, but when the pore diameter is 0.1 μm, the increase is small. This means that clogging is likely to occur with a pore diameter of 1 μm, but
At 0.1 μm, there is less clogging, indicating that when a hollow fiber membrane with a pore size of 0.1 μm is used, radioactive waste liquid filtration treatment can be performed more effectively.

[発明の効果] 以上述べたように、本発明によれば、中空糸膜を使用し
たことにより少ないスペースで濾過面積を大きくするこ
とができ、放射性廃液の濾過処理を効果的に行うことが
できる。また中空糸膜として適切な孔径のものを選定す
れば目詰りを少なくすることができ、膜交換の必要性も
少なくなるの5− で、系統構成も簡単になる。
[Effects of the Invention] As described above, according to the present invention, by using a hollow fiber membrane, the filtration area can be increased in a small space, and radioactive waste liquid can be effectively filtered. . In addition, if a hollow fiber membrane with an appropriate pore size is selected, clogging can be reduced, and the need for membrane replacement can be reduced.5- This also simplifies the system configuration.

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

第1図は放射性廃液中のクラッド粒子分布を示すグラフ
、第2図は本発明の放射性廃液用濾過装置の一実施例を
示?lIR略図、第3図および第4図はそれぞれ孔径1
μmおよび0.1μmの中空糸膜を使用した場合の逆洗
回数と濾過差圧との関係を示すグラフである。 1・・・容器 2・・・モジュール 3・・・放射性廃液流入口 4・・・中空糸膜 5・・・濾液出口 6・・・逆洗水出口 7・・・ベント管代理人弁理士則
 近 憲 佑(1Jか1名)−〇−
Fig. 1 is a graph showing the distribution of clad particles in radioactive waste liquid, and Fig. 2 shows an embodiment of the filtration device for radioactive waste liquid of the present invention. lIR schematic diagrams, Figures 3 and 4 are for pore size 1, respectively.
It is a graph showing the relationship between the number of times of backwashing and the filtration differential pressure when using μm and 0.1 μm hollow fiber membranes. 1... Container 2... Module 3... Radioactive waste liquid inlet 4... Hollow fiber membrane 5... Filtrate outlet 6... Backwash water outlet 7... Vent management agent patent attorney rules Kensuke Chika (1J or 1 person) -〇-

Claims (3)

【特許請求の範囲】[Claims] (1)放射性廃液流入口、i1!液流出口、逆洗水排出
口およびベント管を設置した容器内に、中空糸膜を配設
したことを特徴とする放射性廃液処理用濾過装置。
(1) Radioactive waste liquid inlet, i1! A filtration device for treating radioactive waste liquid, characterized in that a hollow fiber membrane is disposed within a container equipped with a liquid outlet, a backwash water outlet, and a vent pipe.
(2)容器内に複数の中空糸膜のモジコールを吊り下げ
てなる特許請求の範囲第1項記載の放射性廃液処理用濾
過装置。
(2) A filtration device for radioactive waste liquid treatment according to claim 1, comprising a plurality of hollow fiber membranes of Modicol suspended within a container.
(3)中空糸膜が孔径0.1μm前後の多孔質樹脂であ
る特許請求の範囲第1項記載の放射性廃液処理用濾過装
置。
(3) The filtration device for radioactive waste liquid treatment according to claim 1, wherein the hollow fiber membrane is a porous resin with a pore diameter of about 0.1 μm.
JP17917583A 1983-09-29 1983-09-29 Filter for treating radioactive waste liquor Pending JPS6071997A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
JP17917583A JPS6071997A (en) 1983-09-29 1983-09-29 Filter for treating radioactive waste liquor
US06/893,450 US4756875A (en) 1983-09-29 1986-08-07 Apparatus for filtering water containing radioactive substances in nuclear power plants

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP17917583A JPS6071997A (en) 1983-09-29 1983-09-29 Filter for treating radioactive waste liquor

Publications (1)

Publication Number Publication Date
JPS6071997A true JPS6071997A (en) 1985-04-23

Family

ID=16061244

Family Applications (1)

Application Number Title Priority Date Filing Date
JP17917583A Pending JPS6071997A (en) 1983-09-29 1983-09-29 Filter for treating radioactive waste liquor

Country Status (1)

Country Link
JP (1) JPS6071997A (en)

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