JPS6367877B2 - - Google Patents
Info
- Publication number
- JPS6367877B2 JPS6367877B2 JP5528482A JP5528482A JPS6367877B2 JP S6367877 B2 JPS6367877 B2 JP S6367877B2 JP 5528482 A JP5528482 A JP 5528482A JP 5528482 A JP5528482 A JP 5528482A JP S6367877 B2 JPS6367877 B2 JP S6367877B2
- Authority
- JP
- Japan
- Prior art keywords
- liquid
- concentrated
- radioactive
- waste liquid
- ultra
- 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
- 239000007788 liquid Substances 0.000 claims description 39
- 239000012528 membrane Substances 0.000 claims description 15
- 239000000941 radioactive substance Substances 0.000 claims description 14
- 238000000034 method Methods 0.000 claims description 13
- 239000006260 foam Substances 0.000 claims description 11
- 239000004094 surface-active agent Substances 0.000 claims description 9
- 239000002901 radioactive waste Substances 0.000 claims description 8
- 239000012141 concentrate Substances 0.000 claims description 7
- 239000002699 waste material Substances 0.000 claims description 7
- 238000000926 separation method Methods 0.000 claims description 5
- 238000005187 foaming Methods 0.000 claims description 4
- 230000000694 effects Effects 0.000 description 7
- 239000003795 chemical substances by application Substances 0.000 description 6
- 239000000126 substance Substances 0.000 description 6
- 239000012530 fluid Substances 0.000 description 5
- 229920000620 organic polymer Polymers 0.000 description 4
- 239000002244 precipitate Substances 0.000 description 4
- 150000003839 salts Chemical class 0.000 description 4
- 238000000108 ultra-filtration Methods 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- 238000005202 decontamination Methods 0.000 description 3
- 230000003588 decontaminative effect Effects 0.000 description 3
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 3
- 238000002347 injection Methods 0.000 description 3
- 239000007924 injection Substances 0.000 description 3
- 239000007787 solid Substances 0.000 description 3
- 229910018626 Al(OH) Inorganic materials 0.000 description 2
- 238000007664 blowing Methods 0.000 description 2
- 239000000084 colloidal system Substances 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 238000004062 sedimentation Methods 0.000 description 2
- 239000000243 solution Substances 0.000 description 2
- WBIQQQGBSDOWNP-UHFFFAOYSA-N 2-dodecylbenzenesulfonic acid Chemical compound CCCCCCCCCCCCC1=CC=CC=C1S(O)(=O)=O WBIQQQGBSDOWNP-UHFFFAOYSA-N 0.000 description 1
- -1 acrylamide compound Chemical class 0.000 description 1
- 238000005273 aeration Methods 0.000 description 1
- 239000003513 alkali Substances 0.000 description 1
- 238000005345 coagulation Methods 0.000 description 1
- 230000015271 coagulation Effects 0.000 description 1
- 229940060296 dodecylbenzenesulfonic acid Drugs 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-M hydroxide Chemical compound [OH-] XLYOFNOQVPJJNP-UHFFFAOYSA-M 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 230000001151 other effect Effects 0.000 description 1
- 239000012466 permeate Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
- 238000005406 washing Methods 0.000 description 1
- 239000002351 wastewater Substances 0.000 description 1
Landscapes
- Removal Of Specific Substances (AREA)
- Separation Of Suspended Particles By Flocculating Agents (AREA)
Description
【発明の詳細な説明】
本発明は、放射性同位元素取扱施設(以下RI
施設と記す。)から発生する放射性廃液の処理方
法に関する。
従来、当該廃水の処理法として凝集沈殿法、蒸
発法などがある。凝集沈殿法は低コストの方法で
はあるが、除染係数〔DF=(処理前の放射能濃
度)/(処理後の放射能濃度)〕が50以下、減容
比〔CF=(処理前の放射性廃液量)/(処理後の
放射性廃液量)〕が50以下であり、蒸発法は高コ
ストの方法ではあるが、DFが103〜104、CFが
100以下であり、いずれも一長一短がある。
本発明は、比較的低コストで、しかも高いDF
およびCFが得られるRI施設から発生する放射性
廃液の処理方法を提供するものである。
すなわち本発明は、放射性物質を含む廃液をPH
3以上として限外過半透膜で濃縮するか、ある
いは前記廃液をPH3以上とすると共に無機凝集剤
又は有機凝集剤を添加して限外過半透膜で濃縮
し、その濃縮液に界面活性剤を添加して再度前記
限外過半透膜で濃縮し、しかる後その濃縮液を
起泡させて泡沫分離処理することを特徴とする放
射性廃液の処理方法に関するものである。
添付図面は本発明方法の一実施態様例を示す図
である。
図において、まず、放射性廃液5はアルカリ剤
6と混合されながら循環液槽1に入る。アルカリ
剤6は廃液のPHが3以上となるように注入する。
循環液槽1から供給ポンプ4によつて限外過装
置2に圧力送液される(0.5〜4Kg/cm2)。限外
過装置2は溶液中の塩類、溶解した低分子物質を
透過させ、懸濁物質、コロイドおよび高分子物質
は透過させない半透膜による過装置である。半
透膜の穴の大きさは1〜10mμが好ましい。限外
過装置2で一部が透過した透過液8は除染され
た水として放流される。一方、懸濁物質、コロイ
ドなどは透過されず、循環液9に含まれる。循環
液9は、循環液槽1、供給ポンプ4、限外過装
置2の順に循環が続けられ、懸濁物質(放射性物
質を含む)が濃縮される。この濃縮操作は透過液
8中の放射能濃度が所定値(すなわち、放流水の
規準値1×10-6μCi/c.c.)を越えない程度まで続
けられる。このとき減容比は通常50〜100である。
濃縮が進み、適当な減容比が得られると、(なお、
透過液8中の放射能濃度は上記規準値となつた時
点で)界面活性剤7(例えば、ドデシルベンゼン
スルホン酸=DBSなど)を循環液槽1に注入し、
循環を続行する。界面活性剤7の注入率は循環液
槽1に保持されている濃縮液量に対して0.5〜
10ppmとすることが好ましい。循環を5〜10回行
つた後、濃縮液10を泡沫分離装置3に送る。泡
沫分離装置3は空気13によつて濃縮液10を起
泡させる装置である。濃縮液10はその中に含ま
れるDBSと空気によつて液面に多量の泡沫を発
生する。その際、濃縮液10に含まれる懸濁物質
(放射性物質を含む)は気泡面に付着し、スカム
11として濃縮液10の水から分離される。分離
された水は脱離液12として循環液槽1に戻され
る。この分離操作の際、濃縮液10のDBSはほ
とんでがスカム11に移行し、脱離液12には含
まれていない。なお、界面活性剤7を加えなけれ
ば泡沫分離装置3で効果的な泡沫を生じない。
以上の操作により、次のような作用が生じる。
(1) アルカリ剤6を注入して廃液をPH3以上にす
ることにより、放射性物質が不溶化する。たと
えば、 60Co, 59Feの場合、次の反応により、
水酸化物となつて沈殿する。
60Co2++20H-→ 60Co(OH)2(沈殿物)
59Fe3++30H-→ 59Fe(OH)3(沈殿物)
(2) 穴の大きさ1〜10mμの限外過半透膜を使
用することにより、廃液中の懸濁物質および上
記不溶化した放射性物質と液が分離する。
(3) 界面活性剤7を濃縮液量に対し0.5〜10ppm
を加えることにより、半透膜面に付着した懸濁
物質を洗浄脱離させる作用、起泡作用および一
部放射性物質の吸着作用が生じる。
(4) 空気の吹き込みにより、液が起泡され、該気
泡表面に懸濁物質が付着される。なお起泡させ
る方法は、空気吹込みの他に、表面気曝などの
方法がある。
(5) 泡沫分離装置3は発生した気泡とその表面に
付着した懸濁物質などの混合物スカムを液から
分離する。
これらの作用により、次の効果を奏することが
できる。
放射性物質を不溶化して半透膜で分離するこ
とにより高い除染効率が得られる。
界面活性剤を用いることにより分離した放射
性物質を半透膜面から大部分を脱離させ、半透
膜の寿命を延ばすことができる。また半透膜の
くり返し使用ができる。
界面活性剤が一部放射性物質を吸着すること
により除染効率を高める。
泡沫分離することにより液中の放射性物質濃
度を著しく高める。
また本発明方法において、アルカリ剤の添加と
共に、無機凝集剤(例えば、Al塩、Fe塩など)
又は有機高分子凝集剤(例えば、アクリルアミド
化合物など)を添加することもできる。この場
合、アルカリ剤はPH5以上になるように注入率を
決定し、無機擬集剤は凝集剤溶液として50〜
200ppm、有機高分子凝集剤は凝集剤(粉末)と
して0.5〜5ppm添加することが好ましい。
この操作により、次のような作用が生じる。
(i) アルカリ剤の注入により不溶化した放射性物
質が、無機凝集剤又は有機高分子凝集剤により
凝集する。例えば、無機凝集剤(Al塩)の場
合、PH5以上で、次の反応が生じる。
Al3++30H-→Al(OH)3(沈殿物)
上式で生じたAl(OH)3は不溶化した放射性
物質を核として凝集し、粒径が大きくなる。ま
た、有機高分子凝集剤の場合は、不溶化した放
射性物質同志が凝集して粒径が大きくなる。
(ii) その他の作用は前記した(1)〜(5)と同じ。
そして、これらの作用により、次のような効果
を奏することができる。
○
[Detailed Description of the Invention] The present invention is directed to a radioisotope handling facility (hereinafter referred to as RI).
It is written as a facility. ) concerning a method for treating radioactive waste fluid generated from Conventionally, methods for treating the wastewater include a coagulation sedimentation method and an evaporation method. Although the coagulation-sedimentation method is a low-cost method, the decontamination factor [DF = (radioactivity concentration before treatment) / (radioactivity concentration after treatment)] is less than 50, and the volume reduction ratio [CF = (radioactivity concentration before treatment)] is less than 50. (amount of radioactive waste liquid)/(amount of radioactive waste liquid after treatment)] is less than 50, and although the evaporation method is a high-cost method, DF is 10 3 to 10 4 and CF is
100 or less, and each has its advantages and disadvantages. The present invention has relatively low cost and high DF.
The present invention also provides a method for treating radioactive waste fluid generated from RI facilities where CF is obtained. In other words, the present invention can reduce the pH of waste liquid containing radioactive substances.
3 or more and concentrate with an ultra-semi-permeable membrane, or adjust the waste liquid to pH 3 or higher, add an inorganic flocculant or an organic flocculant, concentrate with an ultra-semi-permeable membrane, and add a surfactant to the concentrated liquid. The present invention relates to a method for treating radioactive waste liquid, which is characterized in that the concentrated liquid is added and concentrated again using the ultrasemi-permeable membrane, and then the concentrated liquid is foamed and subjected to foam separation treatment. The accompanying drawings illustrate one embodiment of the method of the present invention. In the figure, radioactive waste liquid 5 first enters circulating liquid tank 1 while being mixed with alkaline agent 6. The alkaline agent 6 is injected so that the pH of the waste liquid becomes 3 or higher.
The circulating liquid tank 1 is fed under pressure (0.5 to 4 kg/cm 2 ) to the ultrafiltration device 2 by the supply pump 4 . The ultrafiltration device 2 is a filtration device using a semipermeable membrane that allows salts in a solution and dissolved low-molecular substances to pass through, but does not allow suspended solids, colloids, and high-molecular substances to pass through. The size of the holes in the semipermeable membrane is preferably 1 to 10 mμ. The permeated liquid 8, which has partially passed through the ultrafiltration device 2, is discharged as decontaminated water. On the other hand, suspended substances, colloids, etc. are not permeated and are included in the circulating fluid 9. The circulating fluid 9 continues to be circulated in the order of the circulating fluid tank 1, the supply pump 4, and the ultrafiltration device 2, and suspended substances (including radioactive materials) are concentrated. This concentration operation is continued until the radioactivity concentration in the permeate 8 does not exceed a predetermined value (ie, the standard value of effluent water, 1×10 −6 μCi/cc). At this time, the volume reduction ratio is usually 50 to 100.
As the concentration progresses and an appropriate volume reduction ratio is obtained (in addition,
When the radioactivity concentration in the permeated liquid 8 reaches the above standard value, a surfactant 7 (for example, dodecylbenzenesulfonic acid = DBS, etc.) is injected into the circulating liquid tank 1,
Continue the cycle. The injection rate of the surfactant 7 is 0.5 to 0.5 to the amount of concentrated liquid held in the circulating liquid tank 1.
It is preferable to set it to 10 ppm. After 5 to 10 cycles, the concentrate 10 is sent to the foam separator 3. The foam separator 3 is a device that foams the concentrated liquid 10 using air 13. The concentrated liquid 10 generates a large amount of foam on the liquid surface due to the DBS and air contained therein. At this time, suspended matter (including radioactive substances) contained in the concentrate 10 adheres to the bubble surface and is separated from the water in the concentrate 10 as scum 11. The separated water is returned to the circulating liquid tank 1 as a desorbed liquid 12. During this separation operation, most of the DBS in the concentrated liquid 10 is transferred to the scum 11 and is not contained in the desorbed liquid 12. Note that unless the surfactant 7 is added, the foam separator 3 will not produce effective foam. The above operations produce the following effects. (1) Radioactive substances are insolubilized by injecting alkaline agent 6 to make the waste liquid pH 3 or higher. For example, in the case of 60 Co and 59 Fe, the following reaction results in
Precipitates as hydroxide. 60 Co 2+ +20H - → 60 Co(OH) 2 (precipitate) 59 Fe 3+ +30H - → 59 Fe(OH) 3 (precipitate) (2) Ultrasemipermeable membrane with hole size 1 to 10 mμ By using this, the suspended solids in the waste liquid and the above-mentioned insolubilized radioactive substances are separated from the liquid. (3) Add surfactant 7 to 0.5 to 10 ppm based on the amount of concentrated liquid.
By adding , the effect of washing and desorbing suspended substances adhering to the semipermeable membrane surface, the foaming effect, and the adsorption effect of some radioactive substances are produced. (4) The liquid is foamed by blowing air, and suspended substances are attached to the surface of the bubbles. In addition to air blowing, there are other methods for foaming, such as surface aeration. (5) The foam separator 3 separates the generated air bubbles and the mixture scum such as suspended solids attached to the surface of the bubbles from the liquid. These actions can provide the following effects. High decontamination efficiency can be obtained by insolubilizing radioactive substances and separating them with a semipermeable membrane. By using a surfactant, most of the separated radioactive substances can be removed from the surface of the semipermeable membrane, thereby extending the life of the semipermeable membrane. Also, the semipermeable membrane can be used repeatedly. Surfactants increase decontamination efficiency by adsorbing some radioactive substances. Separation of foam significantly increases the concentration of radioactive substances in the liquid. In addition, in the method of the present invention, in addition to adding an alkali agent, an inorganic flocculant (for example, Al salt, Fe salt, etc.)
Alternatively, an organic polymer flocculant (eg, an acrylamide compound, etc.) may be added. In this case, the injection rate of the alkaline agent is determined so that the pH is 5 or higher, and the inorganic flocculant is used as a flocculant solution with a pH of 50~
It is preferable to add 200 ppm and 0.5 to 5 ppm of the organic polymer flocculant as a flocculant (powder). This operation produces the following effects. (i) Radioactive substances that have been insolubilized by injection of an alkaline agent are flocculated by an inorganic flocculant or an organic polymer flocculant. For example, in the case of an inorganic flocculant (Al salt), the following reaction occurs at pH 5 or higher. Al 3+ +30H - →Al(OH) 3 (precipitate) The Al(OH) 3 produced in the above equation aggregates with the insolubilized radioactive substance as a core, and the particle size increases. In addition, in the case of an organic polymer flocculant, the insolubilized radioactive substances coagulate together, increasing the particle size. (ii) Other effects are the same as in (1) to (5) above. Through these actions, the following effects can be achieved. ○…
Claims (1)
過半透膜で濃縮し、その濃縮液に界面活性剤を
添加して再度前記限外過半透膜で濃縮し、しか
る後その濃縮液を起泡させて泡沫分離処理するこ
とを特徴とする放射性廃液の処理方法。 2 放射性物質を含む廃液をPH3以上とし、無凝
集剤又は有機凝集剤を添加して限外過半透膜で
濃縮し、その濃縮液に界面活性剤を添加して再度
前記限外過半透膜で濃縮し、しかる後その濃縮
液を起泡させて泡沫分離処理することを特徴とす
る放射性廃液の処理方法。[Scope of Claims] 1 A waste liquid containing a radioactive substance is concentrated with an ultra-semi-permeable membrane to a pH of 3 or more, a surfactant is added to the concentrated liquid, and it is concentrated again with the ultra-semi-permeable membrane, and then the A method for treating radioactive waste liquid, characterized by foaming a concentrated liquid and performing foam separation treatment. 2. Adjust the waste liquid containing radioactive substances to PH3 or higher, add a non-flocculant or an organic flocculant, concentrate with an ultra-semi-permeable membrane, add a surfactant to the concentrated liquid, and re-concentrate it with the ultra-semi-permeable membrane. A method for treating radioactive waste liquid, which comprises concentrating it, and then foaming the concentrated liquid to perform a foam separation treatment.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5528482A JPS58172598A (en) | 1982-04-05 | 1982-04-05 | Method of processing radioactive liquid waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5528482A JPS58172598A (en) | 1982-04-05 | 1982-04-05 | Method of processing radioactive liquid waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58172598A JPS58172598A (en) | 1983-10-11 |
| JPS6367877B2 true JPS6367877B2 (en) | 1988-12-27 |
Family
ID=12994283
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5528482A Granted JPS58172598A (en) | 1982-04-05 | 1982-04-05 | Method of processing radioactive liquid waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58172598A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2562313B1 (en) * | 1984-04-03 | 1989-04-07 | Cogema | PROCESS FOR DECONTAMINATION OF URANIUM AND RADIUM OF ACID URANIFER SOLUTIONS BY ADDITION OF AN ALUMINUM SALT |
| JP5834272B2 (en) * | 2011-09-20 | 2015-12-16 | 株式会社湘南数理研究会 | Decontamination method for contaminated soil |
-
1982
- 1982-04-05 JP JP5528482A patent/JPS58172598A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS58172598A (en) | 1983-10-11 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US7875186B2 (en) | Process for regenerating and protonating a weak-base anion exchange resin | |
| US6372143B1 (en) | Purification of produced water from coal seam natural gas wells using ion exchange and reverse osmosis | |
| US5545309A (en) | Method of processing organic quaternary ammonium hydroxide-containing waste liquid | |
| US20080073275A1 (en) | Bio degradation of oxyanions such as perchlorate on ion exchange resins | |
| JPH1085743A (en) | Method and apparatus for treating water containing boron | |
| JP5189255B2 (en) | Iodine recovery from polarizing film manufacturing wastewater | |
| WO2018096700A1 (en) | System for producing ultrapure water and method for producing ultrapure water | |
| JP2871369B2 (en) | Wastewater treatment method | |
| JPS6367877B2 (en) | ||
| JP7616489B1 (en) | Water treatment device and water treatment method | |
| US4863637A (en) | Process for treating waste liquids of acid decontamination agents | |
| JP5845478B2 (en) | Method and apparatus for treating radioactive material-containing wastewater | |
| JP3119538B2 (en) | Decontamination method for radioactive waste resin | |
| JP2000126766A (en) | Treatment of tetraalkylammonium ion-containing liquid | |
| JP2000301005A (en) | Method for reutilizing effluent in regeneration of ion exchange resin | |
| KR20210033106A (en) | Method for eliminating pollutant from solution | |
| JP2909341B2 (en) | Wastewater treatment equipment | |
| JPH05220479A (en) | Ultrapure water manufacturing system | |
| JP2004028903A (en) | Device for separating radioactive waste liquid and disposal system for radioactive ion exchange resin provided with the same | |
| JP3392483B2 (en) | Treatment method for wastewater containing tetraalkylammonium hydroxide | |
| CN108946869B (en) | A kind of recovery and reuse method of alkalinity in wastewater containing alkalinity | |
| JP2001087795A (en) | Pure water production method and apparatus | |
| JP3467234B2 (en) | How to remove nitrate nitrogen from tap water | |
| JPH11267692A (en) | Treatment of laundry waste liquid | |
| JPH06296993A (en) | Treatment of washing waste water |