JP2992377B2 - Treatment of radioactive liquid waste - Google Patents

Treatment of radioactive liquid waste

Info

Publication number
JP2992377B2
JP2992377B2 JP3211773A JP21177391A JP2992377B2 JP 2992377 B2 JP2992377 B2 JP 2992377B2 JP 3211773 A JP3211773 A JP 3211773A JP 21177391 A JP21177391 A JP 21177391A JP 2992377 B2 JP2992377 B2 JP 2992377B2
Authority
JP
Japan
Prior art keywords
waste liquid
filter
suspended
radioactive
chemical oxygen
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 - Fee Related
Application number
JP3211773A
Other languages
Japanese (ja)
Other versions
JPH0552992A (en
Inventor
恵二朗 安村
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 JP3211773A priority Critical patent/JP2992377B2/en
Publication of JPH0552992A publication Critical patent/JPH0552992A/en
Application granted granted Critical
Publication of JP2992377B2 publication Critical patent/JP2992377B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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  • Water Treatment By Electricity Or Magnetism (AREA)
  • Filtration Of Liquid (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【産業上の利用分野】本発明は原子力施設から発生する
放射性廃液の処理方法に係り、特に衣服の洗濯水,手洗
い,シャワー水等の放射能の低い低レベル放射性廃液の
処理方法に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating radioactive waste liquid generated from nuclear facilities, and more particularly to a method for treating low-level radioactive waste liquid having low radioactivity such as washing water for washing clothes, hand washing and shower water.

【0002】[0002]

【従来の技術】原子力施設、特に原子力発電所では作業
員の使用した衣服の洗濯水や手洗い,シャワー等の廃水
が発生する。このような廃水は放射能濃度が極めて低
く、洗剤成分や糸屑,髪の毛,埃等の浮遊懸濁物質を多
く含み、かつ洗剤成分,シャンプー等による化学的酸素
要求量(COD)が高い。これらの廃液を処理する場
合、従来はストレーナー等により、糸屑等の大きなごみ
を除去した後、放射能を測定し、規定濃度以下の放射能
であることを確認して環境に放出している。
2. Description of the Related Art At a nuclear facility, particularly a nuclear power plant, waste water such as washing water for washing clothes used by workers, hand washing, and showers is generated. Such wastewater has a very low radioactivity concentration, contains a lot of suspended components such as detergent components, lint, hair and dust, and has a high chemical oxygen demand (COD) due to detergent components, shampoos and the like. In the case of treating these waste liquids, conventionally, after removing large waste such as lint with a strainer, the radioactivity is measured, and it is confirmed that the radioactivity is less than the specified concentration and released to the environment. .

【0003】[0003]

【発明が解決しようとする課題】しかしながら、この方
法では、廃液中の微細な浮遊懸濁物質や洗剤,油分等の
化学的酸素要求量の元となる物質の除去はほとんど不可
能であり、環境保全上好ましくない。そこで、これらの
廃水に含まれる微細な浮遊懸濁物質や化学的酸素要求量
の元になる洗剤等の物質を除去する処理方法を試みた。
However, in this method, it is almost impossible to remove fine suspended suspended substances in the waste liquid, substances such as detergents, oils, etc., which cause chemical oxygen demand. Not preferred for conservation. Therefore, a treatment method for removing substances such as a fine suspended suspended substance and a detergent which is a source of chemical oxygen demand contained in these wastewaters was attempted.

【0004】廃水中の浮遊懸濁物質を除去する方法とし
て、けいそう土等の濾材による濾過方法,中空糸膜濾過
器,セラミックス製濾過器による方法がある。また洗剤
等の除去方法として活性炭による除去方法がある。これ
らの方法は以下に記す欠点がある。
As a method for removing suspended suspended substances in wastewater, there are a filtration method using a filter medium such as diatomaceous earth, a hollow fiber membrane filter, and a method using a ceramic filter. As a method for removing detergents and the like, there is a method using activated carbon. These methods have the following disadvantages.

【0005】浮遊懸濁物質をけいそう土でプレコートす
る方法では使用済みのけいそう土は多少ではあるが、放
射能が存在するために一般産業で使用しているように廃
棄ができず、またけいそう土は無機物質であるので焼却
処理も不可能である。他方、中空糸膜フィルタ,セラミ
ックスフィルタ等の非濾材型の濾過器ではこれらの廃水
の性質上濾過時の目詰まりによる処理能力の低下が著し
くて適さない。
[0005] In the method of pre-coating suspended suspended solids with diatomaceous earth, the used diatomaceous earth is slightly discarded because of the presence of radioactivity, as in general industry. Since diatomaceous earth is an inorganic substance, it cannot be incinerated. On the other hand, non-filter material type filters, such as hollow fiber membrane filters and ceramic filters, are not suitable because of the nature of these wastewaters that the processing capacity is significantly reduced due to clogging during filtration.

【0006】また、化学的酸素要求量の主要物質である
洗剤の除去方法として活性炭による吸着が一般に知られ
ている。しかしこの活性炭による除去方法は、活性炭の
吸着力が低下すると活性炭の再生・交換等が必要であ
る。活性炭の再生・交換も一般産業のように容易でない
課題がある。
[0006] As a method of removing a detergent, which is a main substance of the chemical oxygen demand, adsorption by activated carbon is generally known. However, this method of removing with activated carbon requires regeneration and replacement of the activated carbon when the adsorbing power of the activated carbon is reduced. There is a problem that the regeneration and replacement of activated carbon is not as easy as in general industry.

【0007】本発明は上記課題を解決するためになされ
たもので、低レベル放射性廃液から浮遊懸濁物質と化学
的酸素要求物質を効率的に除去することができる放射性
廃液の処理方法を提供することにある。
SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems, and provides a method for treating a radioactive waste liquid capable of efficiently removing suspended suspended substances and chemical oxygen demanding substances from a low-level radioactive waste liquid. It is in.

【0008】[0008]

【課題を解決するための手段】本発明は原子力施設で発
生する洗濯廃液、シャワードレン系廃液等の低レベル放
射性廃液を濾材として高分子繊維が充填されている濾過
器内を通流させて該放射性廃液中の浮遊懸濁物質を除去
した後、その濾液を電気分解槽を通流させて化学的酸素
要求物質を除去することを特徴とする。
According to the present invention, a low-level radioactive waste liquid such as a washing waste liquid or a shower drain waste liquid generated in a nuclear facility is passed through a filter filled with polymer fibers as a filter medium. After removing suspended suspended substances in the radioactive liquid waste, the filtrate is passed through an electrolysis tank to remove chemical oxygen demanding substances.

【0009】[0009]

【作用】低レベル放射性廃液中の浮遊懸濁物質は高分子
繊維濾材で容易に捕獲され、洗剤等の化学的酸素要求量
の主原因となる物質は電気分解法により容易に分解され
て、化学的酸素要求量は低下する。
[Function] Suspended suspended substances in low-level radioactive waste liquid are easily captured by a polymer fiber filter medium, and substances that mainly cause chemical oxygen demand such as detergents are easily decomposed by electrolysis, Oxygen demand is reduced.

【0010】[0010]

【実施例】図1を参照しながら本発明に係る放射性廃液
の処理方法の一実施例を説明する。図1は本発明方法を
実施するための装置の系統図を示している。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of a method for treating radioactive waste liquid according to the present invention will be described with reference to FIG. FIG. 1 shows a system diagram of an apparatus for carrying out the method of the present invention.

【0011】図1中、符号は1は給液タンクで、給液タ
ンク1内には低レベルの放射性試験廃液2が収容されて
いる。給液タンク1の底部には廃液流出管3が接続さ
れ、この廃液流出管3はバルブV1 を介してポンプ4に
接続している。ポンプ4の吐出側には濾材として高分子
繊維が充填された濾過器5に連結する廃液供給管6が接
続されている。濾過器5の出口側は電気分解槽7に濾液
を供給する濾液輸送管8がバルブV2 を介して接続され
ている。上記構成の装置を使用して放射性廃液の浄化処
理を行った結果について説明する。放射性廃液は原子力
発電所から排出される洗濯廃液を試験廃液として使用
し、その試験廃液の組成は表1に示したとおりである。
In FIG. 1, reference numeral 1 denotes a liquid supply tank, and a low level radioactive test waste liquid 2 is stored in the liquid supply tank 1. At the bottom of the supply tank 1 is connected a waste liquid outlet pipe 3, the waste outlet pipe 3 is connected to the pump 4 via a valve V 1. A waste liquid supply pipe 6 connected to a filter 5 filled with polymer fibers as a filter medium is connected to the discharge side of the pump 4. The outlet side of the filter 5 supplies the filtrate filtrate transport pipe 8 is connected via a valve V 2 on the electrolytic cell 7. A description will be given of the result of performing the purification treatment of the radioactive waste liquid using the apparatus having the above configuration. As the radioactive waste liquid, a washing waste liquid discharged from a nuclear power plant is used as a test waste liquid, and the composition of the test waste liquid is as shown in Table 1.

【0012】[0012]

【表1】 [Table 1]

【0013】上記組成の試験廃液を給液タンク1に供給
し、ポンプ4を作動させてバルブV1 ,V2 を開にし、
濾過器5,電気分解槽7に通水を行う。すなわち、ポン
プ4により給液タンク1内の試験廃液2を廃液流出管3
および廃液供給管6を通して濾過器5内に流入する。濾
過器5で濾過された濾液を濾液輸送管8を通して電気分
解槽7内に流入して電気分解する。電気分解された廃液
は出口S2 の排出管から流出される。電気分解槽7にお
ける分解条件は表2に示したとおりである。
The test waste liquid having the above composition is supplied to the liquid supply tank 1, and the pump 4 is operated to open the valves V 1 and V 2 ,
Water is passed through the filter 5 and the electrolysis tank 7. That is, the test waste liquid 2 in the liquid supply tank 1 is discharged by the pump 4
And, it flows into the filter 5 through the waste liquid supply pipe 6. The filtrate filtered by the filter 5 flows into the electrolysis tank 7 through the filtrate transport pipe 8 to be electrolyzed. Electrolyzed effluent is discharged from the discharge pipe outlet S 2. The decomposition conditions in the electrolysis tank 7 are as shown in Table 2.

【0014】[0014]

【表2】 上記操作による濾過器5の出口S1 と電気分解槽7の出
口S2 の浮遊懸濁物質と化学的酸素要求量濃度を測定し
た結果を表3に示す。
[Table 2] Table 3 shows the results obtained by measuring the suspended suspended solids and the chemical oxygen demand concentration at the outlet S 1 of the filter 5 and the outlet S 2 of the electrolysis tank 7 by the above operation.

【0015】[0015]

【表3】 [Table 3]

【0016】表1および表3から明らかなように浮遊懸
濁物質は、給液タンク1内では40ppm であったのが、濾
過器5の出口S1 では6ppm に減少した。また、化学的
酸素要求量(COD)は給液タンク1内では48ppm であ
ったのが、電気分解槽7の出口S2 では4ppm に減少す
ることが認められる。しかして、本発明は濾過器5で浮
遊懸濁物質を減少させ、電気分解槽7で化学的酸素要求
量を分解させることができる。
As is clear from Tables 1 and 3, the suspended suspended substance was reduced from 40 ppm in the feed tank 1 to 6 ppm at the outlet S 1 of the filter 5. The chemical oxygen demand (COD) of was 48ppm in the liquid supply tank 1, it is observed to decrease to 4ppm in outlet S 2 of the electrolysis tank 7. Thus, the present invention can reduce suspended suspended solids in the filter 5 and decompose the chemical oxygen demand in the electrolysis tank 7.

【0017】[0017]

【発明の効果】本発明によれば原子力施設で発生する衣
類の洗濯水,手洗い,シャワー等の放射能濃度のきわめ
て低く、かつ化学的酸素要求量濃度が比較的高い低レベ
ル放射性廃液の処理を容易に行うことができる。
According to the present invention, the treatment of low-level radioactive liquid waste having a very low radioactivity concentration and a relatively high chemical oxygen demand concentration, such as washing water, hand washing, and showers, of clothes generated in a nuclear facility can be performed. It can be done easily.

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

【図1】本発明に係る放射性廃液の処理方法を説明する
ための装置の一例を示す系統図。
FIG. 1 is a system diagram showing an example of an apparatus for explaining a method for treating a radioactive waste liquid according to the present invention.

【符号の説明】[Explanation of symbols]

1…給液タンク、2…試験廃液、3…廃液流出管、4…
ポンプ、5…濾過器、6…廃液供給管、7…電気分解
槽、8…濾液輸送管、V1 ,V2 …バルブ。
1 ... supply tank, 2 ... test waste liquid, 3 ... waste liquid outflow pipe, 4 ...
Pump, 5 ... filter, 6 ... waste supply pipe, 7 ... electrolytic cell, 8 ... filtrate transport tube, V 1, V 2 ... valve.

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】 原子力施設で発生する洗濯廃液、シャワ
ードレン系廃液等の低レベル放射性廃液を濾材として高
分子繊維が充填されている濾過器内を通流させて該放射
性廃液中の浮遊懸濁物質を除去した後、その濾液を電気
分解槽を通流させて化学的酸素要求物質を除去すること
を特徴とする放射性廃液の処理方法。
1. A low-level radioactive waste liquid such as a washing waste liquid or a shower drain waste liquid generated in a nuclear facility is passed through a filter filled with polymer fibers as a filter medium to form a suspended suspension in the radioactive waste liquid. A method for treating a radioactive liquid waste, comprising removing a substance and then passing the filtrate through an electrolysis tank to remove a chemical oxygen demanding substance.
JP3211773A 1991-08-23 1991-08-23 Treatment of radioactive liquid waste Expired - Fee Related JP2992377B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3211773A JP2992377B2 (en) 1991-08-23 1991-08-23 Treatment of radioactive liquid waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3211773A JP2992377B2 (en) 1991-08-23 1991-08-23 Treatment of radioactive liquid waste

Publications (2)

Publication Number Publication Date
JPH0552992A JPH0552992A (en) 1993-03-02
JP2992377B2 true JP2992377B2 (en) 1999-12-20

Family

ID=16611356

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3211773A Expired - Fee Related JP2992377B2 (en) 1991-08-23 1991-08-23 Treatment of radioactive liquid waste

Country Status (1)

Country Link
JP (1) JP2992377B2 (en)

Also Published As

Publication number Publication date
JPH0552992A (en) 1993-03-02

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