JPS5852599A - Treatment of radioactive waste liquid - Google Patents

Treatment of radioactive waste liquid

Info

Publication number
JPS5852599A
JPS5852599A JP15118081A JP15118081A JPS5852599A JP S5852599 A JPS5852599 A JP S5852599A JP 15118081 A JP15118081 A JP 15118081A JP 15118081 A JP15118081 A JP 15118081A JP S5852599 A JPS5852599 A JP S5852599A
Authority
JP
Japan
Prior art keywords
waste liquid
treatment
radioactive waste
organic compounds
treated
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
Application number
JP15118081A
Other languages
Japanese (ja)
Other versions
JPS6051680B2 (en
Inventor
浩 栗林
車田 則充
藤堂 福蔵
英樹 山崎
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.)
JGC Corp
Original Assignee
Japan Gasoline 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 Japan Gasoline Co Ltd filed Critical Japan Gasoline Co Ltd
Priority to JP15118081A priority Critical patent/JPS6051680B2/en
Publication of JPS5852599A publication Critical patent/JPS5852599A/en
Publication of JPS6051680B2 publication Critical patent/JPS6051680B2/en
Expired legal-status Critical Current

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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】 濁または溶存物質を除去して、再使用するための放射性
廃液の処理方法の改良に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an improvement in a method for treating radioactive waste liquid for reuse by removing turbid or dissolved substances.

原子力発電所の廃棄物処理施設に寸6い−ご発生一こる
低レベル放射性廃液は、蒸発濃縮して濃縮廃液は固化処
理し、蒸発した水分は凝縮してイオン交換樹脂で処理し
、再利用している。
The low-level radioactive waste liquid that is generated in the waste treatment facilities of nuclear power plants is evaporated and concentrated, the concentrated waste liquid is solidified, and the evaporated water is condensed and treated with ion exchange resin for reuse. are doing.

ところで、アニオン交換樹脂は一般に熱や放射線に対し
てあまり安定ではなく、一部カー分解してアミン(たと
えばトリメチルアミン)やアルコール(たとえばメタノ
ール)を生成する。 これらの有機化合物はもともと低
沸点であって容易に揮発するし、そのほかの不揮発性の
有機化合物も、蒸発濃縮に際して熱分解されて揮発性成
分を生じたりし、水蒸気とともに凝縮器に送られる。 
凝縮水中に含有された(ほとんど溶解して℃・る)有機
化合物は、一部はイオン交換樹脂に吸着されるが、一部
は吸着されずに処理水中に混入したまま循環する。 吸
着されたものも、イオン交換樹只旨の再生時に放出され
、その再生廃液は上記の廃液処理に際して一緒に処理す
るので、結局は処理水中に移行する。
Incidentally, anion exchange resins are generally not very stable against heat or radiation, and partially decompose to produce amines (eg, trimethylamine) and alcohols (eg, methanol). These organic compounds inherently have low boiling points and easily volatilize, and other non-volatile organic compounds are also thermally decomposed during evaporation and concentration to produce volatile components, which are sent to the condenser along with water vapor.
Some of the organic compounds contained in the condensed water (mostly dissolved at °C) are adsorbed by the ion exchange resin, but some remain unadsorbed and circulate in the treated water. The adsorbed substances are also released when the ion exchange tree is regenerated, and since the regenerated waste liquid is treated together with the above-mentioned waste liquid treatment, it is eventually transferred to the treated water.

このようにして、循環する回収水の中には、次第に有機
化合物が蓄積する傾向があるので、その除去をはからな
ければならない。
In this way, organic compounds tend to gradually accumulate in the recycled recycled water and must be removed.

水中の有機化合物を除去する方法としては、活性炭など
を用いる吸着、エアーストリッピング、および紫外線プ
ラス塩素を用いた酸化分解などがあるが、吸着能率や二
次廃棄物の処理、あるいは装置の腐食といった問題が伴
うので、いずれも放射性廃液の処理には不向きである。
Methods for removing organic compounds from water include adsorption using activated carbon, air stripping, and oxidative decomposition using ultraviolet rays plus chlorine, but there are issues with adsorption efficiency, secondary waste treatment, and equipment corrosion. Both methods are unsuitable for treating radioactive waste fluids due to their associated problems.

今回、本発明者らは、紫外線の照射下に酸化剤とくにオ
ゾンまたは過酸化水素を使用する酸化分解という、上記
のような問題のない廃液中有機化合物の除去を見出し、
これをとりいれた放射性廃液の処理方法を確立したので
、ここに提案する次第である。
This time, the present inventors have discovered a method for removing organic compounds in waste liquid without the above-mentioned problems by oxidative decomposition using an oxidizing agent, particularly ozone or hydrogen peroxide, under irradiation with ultraviolet light.
We have established a method for treating radioactive waste liquid that incorporates this, and we would like to propose it here.

本発明の放射性廃液の処理方法は放射性廃液を蒸発濃縮
して発生する水蒸気を凝縮し回収再使用する処理方法に
おいて、蒸発濃縮を行なう廃液に対し、または蒸発濃縮
の後に得た復水に対し、紫外線を照射しつつ酸化剤を作
用させて、廃液または復水中に含有されている有機化合
物を酸化分解することにより、有機化合物を含まない回
収水を得ることを特命とする。 蒸発濃縮により生じた
濃縮廃液は、固化系へ送って処理すればよい。
The radioactive waste liquid treatment method of the present invention is a treatment method in which the radioactive waste liquid is evaporated and concentrated, and the generated water vapor is condensed and recovered and reused. Our mission is to obtain recovered water that does not contain organic compounds by oxidizing and decomposing organic compounds contained in waste liquid or condensate by applying an oxidizing agent while irradiating ultraviolet rays. The concentrated waste liquid generated by evaporation concentration may be sent to a solidification system for treatment.

酸化剤としては、前述のようにオゾンまたは過酸化水素
を使用するが、とくにアミン等の求電子試薬としてはオ
ゾンが有用である。 これらの酸化剤は、装置を腐食す
るおそれがほとんどなく、しかも使用後は無害な02や
I−1 、O  に分解し、蓄積することがないから、
二次廃棄物の問題も生じない。
As the oxidizing agent, ozone or hydrogen peroxide is used as described above, and ozone is particularly useful as an electrophilic reagent such as an amine. These oxidizing agents have little risk of corroding equipment, and furthermore, after use, they decompose into harmless 02, I-1, and O, and do not accumulate.
There is no problem of secondary waste.

本発明において、紫外線照射下の酸化剤による有機化合
物の酸化分解を、蒸発濃縮に先立って、つまり蒸発濃縮
を行なう廃液を対象にして実施する場合は、第1図に示
すフローの装置を用(・ることになる。
In the present invention, when performing oxidative decomposition of organic compounds using an oxidizing agent under ultraviolet irradiation prior to evaporative concentration, that is, when performing oxidative decomposition of the waste liquid to be evaporated and concentrated, an apparatus having the flow shown in Fig. 1 is used.・It will happen.

すなわち、処理すべき放射性廃液Rwを、まず酸化処理
槽1において、紫外線を照射しつつ酸化剤Oxを作用さ
せてその中の有機化合物を酸化し、流出液を蒸発濃縮装
置2に送る。 酸化剤としてオゾンを空気とともに吹き
込んだ場合は、排ガスを、ミストキャツチャ−3をへて
適宜の排ガス処理装置4に通して処理したのち放出する
。 蒸発濃縮装置2からの濃縮廃液は、濃縮廃液タンク
5に受け、固化工程に送る。 揮発成分は、コンデンサ
6で凝縮してイオン交換樹脂塔7で処理し、回収水タン
ク8に貯えて、循環再使用する。
That is, the radioactive waste liquid Rw to be treated is first irradiated with ultraviolet rays in the oxidation treatment tank 1 and an oxidizing agent Ox is applied thereto to oxidize the organic compounds therein, and the effluent is sent to the evaporation concentration device 2. When ozone is blown in together with air as an oxidizing agent, the exhaust gas is passed through the mist catcher 3 and passed through a suitable exhaust gas treatment device 4 for treatment before being discharged. The concentrated waste liquid from the evaporative concentrator 2 is received in the concentrated waste liquid tank 5 and sent to the solidification process. The volatile components are condensed in a condenser 6, treated in an ion exchange resin tower 7, stored in a recovered water tank 8, and recycled for reuse.

一方、酸化分解を蒸発濃縮の後に、つまり蒸発濃縮で得
た復水を対象に実施する場合は、第2図に示すフローの
装置を用いることになる。 この場合の工程は、上述し
たところと一部の順序が変るだけであるから、再度の説
明を要しないであろう。
On the other hand, when oxidative decomposition is performed after evaporative concentration, that is, when performing oxidative decomposition on condensate obtained by evaporative concentration, an apparatus having the flow shown in FIG. 2 is used. The steps in this case do not need to be explained again because only a part of the order is changed from that described above.

一般に、前者すなわち第1図の態様は、蒸発濃縮時に発
泡性のある廃液または揮発性の有機物を含む廃液に対し
て実施するのが適切であり、また後者つまり第2図の態
様は、蒸発濃縮に際してキヤリ−y  :g−バーずろ
揮発性有機化合物を含む廃液を処理すべき場合に好都合
である。
In general, the former mode, that is, the embodiment shown in Figure 1, is suitable to be carried out on waste liquids that are foamy or contain volatile organic substances during evaporative concentration, and the latter, that is, the embodiment shown in Figure 2, is suitable for evaporative concentration. Carry-y:g-bars are advantageous when waste liquids containing volatile organic compounds are to be treated.

本発明の処理方法は、いうまでもないが、バッチ式、連
続式のいずれでも実施できる。 酸化処理の条件、すな
わち槽内滞留時間、紫外線の強さ、酸化剤の供給量など
は、処理する廃液中に含まれる有機化合物の種類や濃度
によっても異なるが、当業者は、後記する実例を参考に
、必要ならば多少の実験を追加することにより、適切な
条件を容易に見出せるであろう。
Needless to say, the treatment method of the present invention can be carried out either batchwise or continuously. The conditions for oxidation treatment, such as the residence time in the tank, the intensity of ultraviolet rays, and the amount of oxidizing agent supplied, vary depending on the type and concentration of organic compounds contained in the waste liquid to be treated, but those skilled in the art will be able to use the examples given below. For reference, appropriate conditions can be easily found by performing some additional experiments if necessary.

本発明の処理方法により、放射性廃液から、放射性物質
や塩類はもちろん、有機化合物も含まない回収水が得ら
れ、好適に再使用に供することができる。
According to the treatment method of the present invention, recovered water containing not only radioactive substances and salts but also organic compounds can be obtained from radioactive waste liquid, and can be suitably reused.

このようにして、本発明によれば、原子力発電所の廃棄
物処理施設における放射性廃液の処理に関し、クローズ
ドシステムが実現する。
In this way, according to the invention, a closed system is realized for the treatment of radioactive waste liquid in the waste treatment facility of a nuclear power plant.

実施例 第1図に示す構成の装置を用いて、イオン交換樹脂の乾
燥工程において発生する復水を、5t/時(7) がわかった。
EXAMPLE Using an apparatus having the configuration shown in FIG. 1, it was found that the amount of condensate generated in the drying process of ion exchange resin was 5 tons/hour (7).

の割合で処理した。 この廃液は、有機化合物としてI
・リメチルアミン300ppm  およげメタノール1
.5Orlr1m  を含有している。
It was treated at a rate of This waste liquid contains I as an organic compound.
・Remethylamine 300ppm and methanol 1
.. Contains 5Orlr1m.

酸化処理槽は容積]、 Otで、底部に散気管を有して
おり、これを通して、オゾンを含む空気をオゾン量にし
て0.5f/分の速度で供給しつつ、出力】00W の
水銀ランプからの紫外線を照射した。
The oxidation treatment tank has a volume of 100 W and has an aeration tube at the bottom, through which air containing ozone is supplied at a rate of 0.5 f/min, and a mercury lamp with an output of 00 W is supplied. irradiated with ultraviolet light from

槽からの流出液中のトリメチルアミンおよびメタノール
の分解率は、ともに約99%であった。
The decomposition rates of trimethylamine and methanol in the effluent from the tank were both about 99%.

これを蒸発濃縮して得た復水中の有機化合物は、検出限
界以内であった。 以下、これを常法に従ってイオン交
換樹脂で処理した処理水は、再利用上全く問題のないも
のであった。
The organic compounds in the condensate obtained by evaporation and concentration were within the detection limit. Hereinafter, the treated water was treated with an ion exchange resin according to a conventional method, and there was no problem in terms of reuse.

実際的な操業条件または装置の能力の限界を知るために
、メタノール170ppm  を含有する廃液を処理の
対象とし、酸化処理槽内の液滞留時間を短縮して行った
ところ、第3図に示すメタノール分解率を得た。 この
グラフから、使用した装置においては、60分以上80
分程度の液滞留時間を与えれば、はぼ完全に酸化分解が
行なえること(8)
In order to understand the practical operating conditions or the limits of the equipment's capacity, we treated a waste liquid containing 170 ppm of methanol and shortened the residence time of the liquid in the oxidation treatment tank. The decomposition rate was obtained. From this graph, it can be seen that in the device used, 80
Almost complete oxidative decomposition can be achieved by giving a liquid residence time of about 1 minute (8)

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

第1図および第2図は、ともに本発明の放射性廃液の処
理方法を説明するためのフローチャートであって、 第1図は、有機化合物の酸化分解を蒸発濃縮操作にかけ
る前の廃液に対して行なう態様を、また第2図は、有機
化合物の酸化分解を蒸発濃縮操作によって得た復水に対
して行なう態様を、それぞれ示す。 第3図は、本発明の実施例の効果を示すグラフである。 1・・・・・・酸化処理槽 2・・・・・・蒸発濃縮装置 6・・・・・ コンデンサ 7・・ ・ イオン交換樹脂塔 特許出願人 日揮株式会社
1 and 2 are flowcharts for explaining the radioactive waste liquid treatment method of the present invention. FIG. 2 shows a mode in which the oxidative decomposition of an organic compound is carried out on condensate obtained by an evaporative concentration operation. FIG. 3 is a graph showing the effects of the embodiment of the present invention. 1... Oxidation treatment tank 2... Evaporation concentration device 6... Condenser 7... Ion exchange resin column patent applicant JGC Corporation

Claims (5)

【特許請求の範囲】[Claims] (1)放射性廃液を蒸発濃縮して発生する水蒸気を凝縮
し回収再使用する処理方法において、蒸発濃縮を行なう
廃液に対し、または蒸発濃縮の後に得た復水に対し、紫
外線を照射しつつ酸化剤を作用させて、廃液または復水
中に含有されている有機化合物の酸化分解を行なって回
収水を得ることを特徴とする放射性廃液の処理方法。
(1) In a treatment method in which the water vapor generated by evaporating and concentrating radioactive waste liquid is condensed and recovered for reuse, the waste liquid undergoing evaporative concentration or the condensate obtained after evaporative concentration is oxidized while being irradiated with ultraviolet rays. 1. A method for treating radioactive waste liquid, which comprises oxidizing and decomposing organic compounds contained in the waste liquid or condensate by applying an agent to obtain recovered water.
(2)酸化剤としてオゾンまたは過酸化水素を使用する
特許請求の範囲第1項の処理方法。
(2) The treatment method according to claim 1, wherein ozone or hydrogen peroxide is used as the oxidizing agent.
(3)廃液または復水中に含有されている有機化合物を
、まず酸化剤を作用させてその一部を酸化分解し、つい
で紫外線を照射しつつ酸化剤を作用させて残りを分解す
る二段法による特許請求の範囲第1項の処理方法。
(3) A two-step method in which organic compounds contained in waste liquid or condensate are first treated with an oxidizing agent to oxidize and decompose a portion of them, and then irradiated with ultraviolet rays and treated with an oxidizing agent to decompose the remainder. The processing method according to claim 1.
(4)有機化合物を含む放射性廃液が、放射性イオン交
換樹脂の乾燥により発生する蒸気を凝縮して得た放射性
廃液である特許請求の範囲第1項の処理方法。
(4) The treatment method according to claim 1, wherein the radioactive waste liquid containing an organic compound is a radioactive waste liquid obtained by condensing vapor generated by drying a radioactive ion exchange resin.
(5)蒸発濃縮工程で発生した濃縮廃液を固化系へ送っ
て処理する工程を含む特許請求の範囲第1項の処理方法
(5) The treatment method according to claim 1, which includes a step of sending the concentrated waste liquid generated in the evaporation concentration step to a solidification system for treatment.
JP15118081A 1981-09-24 1981-09-24 How to dispose of radioactive waste liquid Expired JPS6051680B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP15118081A JPS6051680B2 (en) 1981-09-24 1981-09-24 How to dispose of radioactive waste liquid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP15118081A JPS6051680B2 (en) 1981-09-24 1981-09-24 How to dispose of radioactive waste liquid

Publications (2)

Publication Number Publication Date
JPS5852599A true JPS5852599A (en) 1983-03-28
JPS6051680B2 JPS6051680B2 (en) 1985-11-15

Family

ID=15513039

Family Applications (1)

Application Number Title Priority Date Filing Date
JP15118081A Expired JPS6051680B2 (en) 1981-09-24 1981-09-24 How to dispose of radioactive waste liquid

Country Status (1)

Country Link
JP (1) JPS6051680B2 (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4624792A (en) * 1983-12-12 1986-11-25 Jgc Corporation Method for treating radioactive organic wastes
US4693833A (en) * 1984-10-26 1987-09-15 Jgc Corporation Method of treating radioactive waste water resulting from decontamination
US4737315A (en) * 1983-06-08 1988-04-12 Jgc Corporation Method of treating radioactive organic wastes
US4877558A (en) * 1986-08-20 1989-10-31 Fuji Electric Co., Ltd. Method of treating radioactive ion-exchange resins by oxidative decomposition
EP1262231A1 (en) * 2001-05-29 2002-12-04 Commissariat A L'energie Atomique Process and apparatus for selective elimination of functional organic compounds from a liquid medium

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4737315A (en) * 1983-06-08 1988-04-12 Jgc Corporation Method of treating radioactive organic wastes
US4624792A (en) * 1983-12-12 1986-11-25 Jgc Corporation Method for treating radioactive organic wastes
US4693833A (en) * 1984-10-26 1987-09-15 Jgc Corporation Method of treating radioactive waste water resulting from decontamination
US4877558A (en) * 1986-08-20 1989-10-31 Fuji Electric Co., Ltd. Method of treating radioactive ion-exchange resins by oxidative decomposition
EP1262231A1 (en) * 2001-05-29 2002-12-04 Commissariat A L'energie Atomique Process and apparatus for selective elimination of functional organic compounds from a liquid medium
FR2825294A1 (en) * 2001-05-29 2002-12-06 Commissariat Energie Atomique METHOD AND DEVICE FOR SELECTIVELY ELIMINATING FUNCTIONALIZED ORGANIC COMPOUNDS FROM A LIQUID MEDIUM
JP2003103109A (en) * 2001-05-29 2003-04-08 Commiss Energ Atom Method and apparatus for selectively removing organic compound having functional group in liquid medium
US6913699B2 (en) 2001-05-29 2005-07-05 Commissariat Energie Atomique Process for selectively removing functionalized organic compounds from a liquid medium
JP4551052B2 (en) * 2001-05-29 2010-09-22 コミッサリア ア レネルジー アトミーク エ オ ゼネルジ ザルタナテイヴ Method and apparatus for selectively removing an organic compound having a functional group in a liquid medium

Also Published As

Publication number Publication date
JPS6051680B2 (en) 1985-11-15

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