JPS62110195A - Method of processing radioactive concentrated waste liquor - Google Patents
Method of processing radioactive concentrated waste liquorInfo
- Publication number
- JPS62110195A JPS62110195A JP25046885A JP25046885A JPS62110195A JP S62110195 A JPS62110195 A JP S62110195A JP 25046885 A JP25046885 A JP 25046885A JP 25046885 A JP25046885 A JP 25046885A JP S62110195 A JPS62110195 A JP S62110195A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- concentrated waste
- radioactive
- waste liquor
- sodium nitrate
- 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
Links
Landscapes
- Fertilizers (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】
〔産業上の利用分野〕
本発明は、再処理工場で生じる放射性廃液の処理方法に
関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a method for treating radioactive waste liquid produced in a reprocessing plant.
再処理工場で生じる放射性物質およびＣＯＤ成分（化学
的酸素要求量Ｃｈｅｍｉｃａｌ Ｏｘｙｇｅｎ Ｄｅｍ
ａｎｄ）を含有する硝酸す） ＩＪウム濃縮廃液を浄化
し。Radioactive substances and COD components (Chemical Oxygen Dem
Purify the concentrated waste liquid containing nitric acid and).
硝酸ナトリウムを無害なものとして海洋に放出しようと
する試みはこれまでになされていない。No attempt has been made to release sodium nitrate into the ocean as a harmless substance.
〔発明が解決しようとする問題点０
階 放射性の濃縮廃液を浄化し、硝酸ナトリウムを無害
なものとして海洋に放出するためには、放射能およびＣ
ＯＤ成分のみ選択的に分離する必要がある。[Problem to be solved by the invention Floor 0 In order to purify radioactive concentrated waste liquid and release sodium nitrate into the ocean as harmless, it is necessary to eliminate radioactivity and carbon dioxide.
It is necessary to selectively separate only the OD component.
本発明は、上記要請に対応できる処理方法を提供するこ
とを目的とする。An object of the present invention is to provide a processing method that can meet the above requirements.
本発明の特徴は濃縮廃液（硝酸ナトリウム。 The feature of the present invention is concentrated waste liquid (sodium nitrate).
トリブチルホスフェート、放射能）より、海洋放出に対
して問題となるトリブチルホスフェート、放射性物質を
選択的に除去する方法として。As a method to selectively remove tributyl phosphate, a radioactive substance that poses a problem when released into the ocean.
限外濾過膜、無機イオン交換体、および電気透析法を組
合せて適用した点にある。The point is that an ultrafiltration membrane, an inorganic ion exchanger, and an electrodialysis method are applied in combination.
これにより本濃縮廃液中の硝酸すｌ−ＩＪウムは浄化さ
れ、海岸に放出可能となる。As a result, the sulfur-IJium nitrate in the concentrated waste liquid is purified and can be discharged onto the coast.
本発明方法においては、まず限外濾過膜で含有する懸濁
物質を取り除き２次に無機イオン交換体で放射性金属イ
オン等を除去し、さらに電気透析法でＮａ＋、 ＮＯ３
−等を廃液から抽出して浄化液として回収し、海洋に投
棄可能としている。In the method of the present invention, suspended solids are first removed using an ultrafiltration membrane, radioactive metal ions, etc. are removed using an inorganic ion exchanger, and then Na+ and NO3 are removed using an electrodialysis method.
-, etc. are extracted from the waste liquid and recovered as a purification liquid, which can then be dumped into the ocean.
次に本発明方法の一実施例を図面に基いて説明する。 Next, an embodiment of the method of the present invention will be explained based on the drawings.
第１図において、濃縮廃液ｌ（硝酸ナトリウムＮａＮＯ
３、） ！Ｊブチルホスフェート、放射能核種）はＰＨ
調整用の酸２で酸性に調整され、放射性金属の内水酸化
物を形成するものは沈澱させる。この液は原液移送ポン
プ３で限外沖過膜モジュー／Ｌ／ ４に通水されここで
、濃縮された液５（水酸化物および濃縮廃ｉ１に元々含
有される懸濁物質）は蒸発器１２に送られる。In Figure 1, concentrated waste liquid l (sodium nitrate NaNO
3,)! J-butyl phosphate, radionuclide) is PH
The acidity is adjusted with adjusting acid 2, and radioactive metals that form hydroxides are precipitated. This liquid is passed through the ultrafiltration membrane module/L/4 by the raw liquid transfer pump 3, where the concentrated liquid 5 (hydroxide and suspended solids originally contained in the concentrated waste i1) is transferred to the evaporator. Sent to 12th.
一方限外濾過膜モジュー／ｖ４を透過した液６（ＮａＮ
Ｏ３、） ’） ７” ｆ ）Ｖ ホ ス ７
ｘ −ト （ｔｒｙｂｕｔｈｙｌｐｈｏｓｆａｔｅ
）およびイオン性の放射能）は、無機イオン交換体（
放射性金属イオン除去用）７で放射性金属イオンが、無
機イオン交換体（ヨウ素除去用）８でヨウ素イオンが除
去される。On the other hand, liquid 6 (NaN
O3, ) ') 7” f ) V Hoss 7
x -t (trybuthylphosfate
) and ionic radioactivity) are inorganic ion exchangers (
Radioactive metal ions are removed in 7 (for radioactive metal ion removal), and iodine ions are removed in an inorganic ion exchanger (for iodine removal) 8.
この液は更に電気透析槽９に通水される。電気透析槽９
では陽イオン交換膜によりＮａ＋が。This liquid is further passed through the electrodialyzer 9. Electrodialysis tank 9
Then, Na+ is generated by the cation exchange membrane.
陰イオン交換膜によりＮＯ３−がその他の溶質（トリブ
チルホスフェート、無機イオン交換体をリークした放射
性イオン）より分離され、浄化液（硝酸ナトリウム液）
１１として回収され、これはモニター後、海洋に放出さ
れる。NO3- is separated from other solutes (tributyl phosphate, radioactive ions that leaked from the inorganic ion exchanger) by an anion exchange membrane, and a purification solution (sodium nitrate solution) is removed.
11, which will be monitored and released into the ocean.
一方、電気透析槽９の廃液（トリブチルホスフェート、
放射性イオン）１０は蒸発器１２に送られ濃縮処理され
る。On the other hand, the waste liquid from the electrodialysis tank 9 (tributyl phosphate,
The radioactive ions) 10 are sent to an evaporator 12 and concentrated.
〈実施例〉
放射性濃縮廃液を第１図の方法にて処理した場合の効果
を次表に示す。<Example> The following table shows the effects when radioactive concentrated waste liquid is treated by the method shown in Figure 1.
第１表
又、各単体器機での除染係数ＤＦ
（Ｄｅｃｏｎｔａｍｉｎａｔｉｏｎ Ｆａｃｔｏｒ ）
を次に示す。Table 1 also shows the decontamination factor DF (Decontamination Factor) for each single device.
is shown below.
限外濾過モジュ−／Ｌ’４ Ｄ Ｆ ＝ １０無
機イオン交換体７，８ ＤＦ＝１０４電気透析槽９
Ｄ Ｆ ＝ １０〔発明の効果〕
以上のように本発明によれば、放射性の濃縮廃液より硝
酸ナトリウムのみを抽出除去することにより、廃液１０
中の塩濃度を約１／１０に低減できるため、蒸発器１２
における濃縮倍率を従来より約１０倍上げることができ
、結果的に廃棄物発生量を無処理の場合に比較して約１
／１０に減少することができる。Ultrafiltration module/L'4 DF = 10 Inorganic ion exchanger 7,8 DF = 104 Electrodialysis tank 9
D F = 10 [Effect of the Invention] As described above, according to the present invention, by extracting and removing only sodium nitrate from radioactive concentrated waste liquid, waste liquid 10
The salt concentration in the evaporator 12 can be reduced to about 1/10.
It is possible to increase the concentration ratio by about 10 times compared to conventional methods, and as a result, the amount of waste generated is reduced by about 1 compared to the case without treatment.
/10.
第１図は本発明の一実施例としての放射性濃縮廃液処理
のフロー図である。FIG. 1 is a flow diagram of radioactive concentrated waste liquid treatment as an embodiment of the present invention.
Claims (1)
濃縮廃液を限外ろ過膜、無機イオン交換体、および電気
透析法を組み合せた方法にて処理し、硝酸ナトリウムを
放射性物質およびＣＯＤ成分を含有しない無害な形で抽
出することを特徴とする放射性濃縮廃液の処理方法。Concentrated sodium nitrate waste liquid containing radioactive substances and COD components is treated using a method that combines an ultrafiltration membrane, an inorganic ion exchanger, and an electrodialysis method to convert sodium nitrate into a harmless form that does not contain radioactive substances and COD components. A method for treating radioactive concentrated waste liquid, which is characterized by extraction with.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP25046885A JPS62110195A (en) | 1985-11-08 | 1985-11-08 | Method of processing radioactive concentrated waste liquor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP25046885A JPS62110195A (en) | 1985-11-08 | 1985-11-08 | Method of processing radioactive concentrated waste liquor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62110195A true JPS62110195A (en) | 1987-05-21 |
Family
ID=17208317
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP25046885A Pending JPS62110195A (en) | 1985-11-08 | 1985-11-08 | Method of processing radioactive concentrated waste liquor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62110195A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007064344A (en) * | 2005-08-31 | 2007-03-15 | Nlm Ecal Co Ltd | Pedestal |
| JP2013108818A (en) * | 2011-11-21 | 2013-06-06 | Hitachi-Ge Nuclear Energy Ltd | Radioactive waste liquid treatment method and treatment system |
| CN106683732A (en) * | 2016-12-23 | 2017-05-17 | 岭东核电有限公司 | Equipment and method for treating radioactive wastewater |
-
1985
- 1985-11-08 JP JP25046885A patent/JPS62110195A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007064344A (en) * | 2005-08-31 | 2007-03-15 | Nlm Ecal Co Ltd | Pedestal |
| JP2013108818A (en) * | 2011-11-21 | 2013-06-06 | Hitachi-Ge Nuclear Energy Ltd | Radioactive waste liquid treatment method and treatment system |
| CN106683732A (en) * | 2016-12-23 | 2017-05-17 | 岭东核电有限公司 | Equipment and method for treating radioactive wastewater |
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