JPH01311296A - Processing method for waste solvent - Google Patents
Processing method for waste solventInfo
- Publication number
- JPH01311296A JPH01311296A JP63142398A JP14239888A JPH01311296A JP H01311296 A JPH01311296 A JP H01311296A JP 63142398 A JP63142398 A JP 63142398A JP 14239888 A JP14239888 A JP 14239888A JP H01311296 A JPH01311296 A JP H01311296A
- Authority
- JP
- Japan
- Prior art keywords
- tbp
- separated
- water
- dodecane
- solvent
- 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
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
Abstract
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、燃料製造工場等の溶媒抽出工程で
使用した廃溶媒の精製、再利用および処分のためＴＢＰ
（リン酸トリー〇ブチル）等とｎ・ドデカン等を分離す
る場合や、ＴＢＰに同伴する不純物のＤＢＰ （ジエス
テル）、ＭＢＰ（モノエステル）等を除去し、精製する
場合に利用できる廃溶媒の処理方法に関する。[Detailed Description of the Invention] [Industrial Application Field] The present invention provides TBP for purification, reuse, and disposal of waste solvents used in solvent extraction processes at reprocessing plants, fuel manufacturing plants, etc.
Treatment of waste solvents that can be used to separate n-dodecane, etc. from (tri-butyl phosphate), etc., and to remove and purify impurities such as DBP (diester) and MBP (monoester) accompanying TBP. Regarding the method.
再処理工場、燃料製造工場等の抽出工程から発生する廃
溶媒は、主としてＴＢＰ等とｎ・ドデカン等の混合物よ
りなっている。Waste solvents generated from extraction processes at reprocessing plants, fuel manufacturing plants, etc. mainly consist of a mixture of TBP and the like and n-dodecane and the like.
従来、ＴＢＰ等とｎ・ドデカン等の分離のために、
■茎溜して分離する方法、
■廃液に濃リン酸溶液を加え、リン酸−ＴＢＰ付加付加
水てｎ・ドデカン等から分離し、さらにリン酸−ＴＢＰ
付加付加水を添加して水に難溶なＴＢＰと希すン酸？′
８液にして分離する方法、■廃溶媒に中和剤を混合して
から焼却する方法、等が提案されている。Conventionally, in order to separate TBP, etc. and n-dodecane, etc., there are two methods: 1. A method of collecting and separating TBP, 2. A concentrated phosphoric acid solution is added to the waste liquid, and phosphoric acid-TBP is separated from n-dodecane, etc. using added water. Furthermore, phosphoric acid-TBP
Is it possible to add TBP and dilute sulfuric acid, which are poorly soluble in water, by adding additional water? ′
Proposed methods include separating the solvent into eight liquids, and (2) mixing a neutralizing agent with the waste solvent and then incinerating it.
また、ＴＢＰの精製は従来２０％ＮａＯＨで中和洗浄し
、水、ＤＢＰＳＭＢＰ等を除去し、次いで常圧蒸溜し、
ブタノール、水等を除去し、さらに真空蒸溜して微量の
ブタノール、水、ＤＢＰ。Conventionally, TBP is purified by neutralizing and washing with 20% NaOH to remove water, DBPSMBP, etc., and then distilling at atmospheric pressure.
Butanol, water, etc. are removed and further vacuum distilled to produce trace amounts of butanol, water, and DBP.
ＭＢＰを除去することが行われている。Efforts are being made to remove MBP.
しかしながら、■の方法では含有されている溶媒に起因
する火災、爆発等の発生に対する防止策を施すことが必
要となり、■の方法では腐食性の大きなリン酸を使用す
るため使用する機械の材質に困難さがあり、使用済のリ
ン酸の処分が問題となる。また、■の方法では煙に包ま
れる微粒子のため排ガス処理系がすぐ目詰まり起こして
しまうという欠点がある。However, method (■) requires measures to prevent fires, explosions, etc. caused by the solvent contained, and method (■) uses phosphoric acid, which is highly corrosive, so the material of the machine used may be affected. There are difficulties, and disposal of used phosphoric acid becomes an issue. In addition, the method (2) has the disadvantage that the exhaust gas treatment system is easily clogged due to the particulates engulfed in smoke.
また、従来のＴＢＰの精製は処理工程が複雑であるとい
う欠点があった。Furthermore, conventional purification of TBP has the disadvantage that the processing steps are complicated.
本発明は上記問題点を解決するためのもので、腐食の問
題をなくし、処理工程が箇華で、ＴＢＰ等の再利用を容
易に行うことができる廃溶媒の処理方法を提供すること
を目的とする。The present invention is intended to solve the above-mentioned problems, and aims to provide a method for treating waste solvents that eliminates the problem of corrosion, has a simple treatment process, and allows easy reuse of TBP, etc. do.
そのために本発明は、再処理工場、燃料製造工場等の溶
媒抽出工程から発生する放射性廃溶媒の処理方法におい
て、凍結・昇華工程、昇華した蒸発物質をａ縮分離する
工程、昇華しない残留物を分離回収する工程を含むこと
を特徴とする。To this end, the present invention provides a method for treating radioactive waste solvents generated from solvent extraction processes at reprocessing plants, fuel manufacturing plants, etc., including a freezing/sublimation process, a condensation separation process for sublimated evaporated substances, and a process for removing non-sublimated residues. It is characterized by including a step of separating and recovering.
本発明の廃溶媒の処理方法は、凍結真空乾燥法を用いて
凍結、昇華させることにより、廃溶媒を硝酸、水、昇華
する核種、ｎ・ドデカン等よりなる凝縮液と、ＴＢＰ、
ＤＢＰ、ＭＢＰおよび蒸発しない核燃料物質、核分裂生
成物を含む残留物とに分離し、昇華した蒸発物質を比重
差を利用して凝縮分離し、昇華しない残留物を中和洗浄
により溶媒と該溶媒に同伴する物質とに分離するもので
あり、装置構成材料に腐食の問題が生じる高温を利用せ
ず、低温を利用し、腐食、火災、爆発等の発生の恐れを
なくし、安全性を一層高くすることが可能となる。The waste solvent treatment method of the present invention involves freezing and sublimating the waste solvent using a freeze-vacuum drying method, thereby converting the waste solvent into a condensate consisting of nitric acid, water, a sublimating nuclide, n-dodecane, etc., TBP,
DBP, MBP and nuclear fuel material that does not evaporate and residues containing fission products are separated, the sublimed evaporated material is condensed and separated using the difference in specific gravity, and the non-sublimated residue is washed with a solvent by neutralization washing. It is separated from accompanying substances, and uses low temperatures instead of high temperatures that can cause problems of corrosion in equipment constituent materials, eliminating the risk of corrosion, fire, explosion, etc., and further increasing safety. becomes possible.
以下、実施例を図面に基づき説明する。 Examples will be described below based on the drawings.
第１図は本発明の廃溶媒処理の全体構成を示す図である
。ｌは凍結乾燥器、２は廃溶媒、３は冷媒、４は加熱媒
体、５は凝縮器、６は真空ポンプ、７は冷媒、８は凝縮
液受槽、９は有機相、１０は水相、１１はｎドデカン等
、１２は水・硝酸等、１３はＴＢＰ・核燃料物質・核分
裂生成物である。FIG. 1 is a diagram showing the overall configuration of waste solvent treatment according to the present invention. 1 is a freeze dryer, 2 is a waste solvent, 3 is a refrigerant, 4 is a heating medium, 5 is a condenser, 6 is a vacuum pump, 7 is a refrigerant, 8 is a condensate receiver, 9 is an organic phase, 10 is an aqueous phase, 11 is n-dodecane, etc., 12 is water, nitric acid, etc., and 13 is TBP, nuclear fuel material, nuclear fission products.
図において、凍結乾燥器ｌへは廃溶媒供給系から廃溶媒
２が供給されるようになっている。凍結乾燥器１へは冷
媒３、加熱媒体４が供給排出され、廃溶媒２を冷却凍結
、昇華乾燥するようになっている。凍結乾燥器ｌで昇華
した物質は凝縮器５に供給される。凝縮器５には冷媒７
が供給排出されると共に、真空ポンプ６で排気されてお
り、凝縮液は凝縮液受槽８へ貯留し、比重差により有機
相９と水相１０とに分離し、それぞれ有機相からはｎド
デカン等１１が抽出され、水相１０からは水・硝酸等１
２が抽出される。また凍結乾燥器ｌで蒸発しないＴＢＰ
・核燃料物質・核分裂生成物１３は残留物として取り出
され、後述するように中和洗浄すると共に、さらに分離
されて再利用、廃棄系へ導かれることになる。In the figure, a waste solvent 2 is supplied to the freeze dryer 1 from a waste solvent supply system. A refrigerant 3 and a heating medium 4 are supplied to and discharged from the freeze dryer 1, and the waste solvent 2 is cooled, frozen, and sublimated to dry. The substance sublimed in the freeze dryer 1 is supplied to the condenser 5. Refrigerant 7 is in the condenser 5.
is supplied and discharged, and exhausted by a vacuum pump 6, and the condensate is stored in a condensate receiving tank 8 and separated into an organic phase 9 and an aqueous phase 10 due to the difference in specific gravity, and n-dodecane, etc. are extracted from the organic phase. 11 is extracted, and water, nitric acid, etc. 1 are extracted from the aqueous phase 10.
2 is extracted. Also, TBP that does not evaporate in a freeze dryer
- The nuclear fuel material/fission product 13 is taken out as a residue, neutralized and cleaned as described later, and further separated and guided to a reuse and disposal system.
こうして、ＴＢＰ等、ｎ・ドデカン等、核燃料物質、核
分裂生成物、硝酸、水等が再処理工場、燃料製造工場等
の溶媒抽出工程からｉＪ）出され、再生もしくは廃棄さ
れる。In this way, nuclear fuel materials such as TBP, n-dodecane, nuclear fission products, nitric acid, water, etc. are discharged from the solvent extraction process of reprocessing plants, fuel manufacturing plants, etc., and are recycled or disposed of.
次に、第２図を参照して廃溶媒のプロセスフローについ
て説明する。Next, the waste solvent process flow will be explained with reference to FIG.
第２図はプロセスフローを説明するための図である。■
は廃溶媒、■は冷媒、■は加熱媒体、■はＴＢＰ等残留
物、■は中和洗浄工程、■は凝縮器および凝縮液、■は
ｎ・ドデカン等、■は水・硝酸等、■はＴＢＰ、［相］
はＮａＯＨ溶液、■は再利用又は廃液系、■は廃液処理
系である。FIG. 2 is a diagram for explaining the process flow. ■
is waste solvent, ■ is refrigerant, ■ is heating medium, ■ is residue such as TBP, ■ is neutralization cleaning process, ■ is condenser and condensate, ■ is n/dodecane, etc., ■ is water/nitric acid, etc. is TBP, [phase]
is a NaOH solution, ■ is a reuse or waste liquid system, and ■ is a waste liquid treatment system.
図において、工程で排出された廃溶媒■は、凍結工程■
において冷却凍結される。凍結された廃溶媒凍結体は昇
華工程■において加熱・減圧され、真空状態に置かれて
凍結体より廃溶媒中に含まれている硝酸、水、ｎ・ドデ
カン等と昇華する核種が昇華され、それらは凝縮器■で
凝縮され、凝縮液として抽出される。凝縮液は工程■、
■で有機相のｎ・ドデカン等と水相の硝酸、水等に分離
されてそれぞれ処理される。In the figure, the waste solvent discharged in the process ■ is the freezing process ■
It is cooled and frozen. The frozen waste solvent frozen body is heated and depressurized in the sublimation process ①, and placed in a vacuum state, and the nuclides that sublimate with nitric acid, water, n-dodecane, etc. contained in the waste solvent are sublimed from the frozen body, They are condensed in the condenser ① and extracted as a condensate. The condensate is the process■,
In step (2), the organic phase is separated into an organic phase such as n-dodecane, and an aqueous phase such as nitric acid and water, and each is treated separately.
一方、ＴＢＰ、ＤＢＰ、ＭＢＰ等と共に昇華しない核燃
料物質、核分裂物質等は工程■でＴＢＰ等残留物として
取り出される。On the other hand, nuclear fuel materials, fissile materials, etc. that do not sublimate together with TBP, DBP, MBP, etc. are taken out as residues such as TBP in step (2).
取り出されたＴＢＰ等残留物質は、中和洗浄工程■にお
いて約２０％の？１ＮａＯＨ溶液で中和洗浄されて、工
程■と［相］において、ＴＢＰと核燃料物質、核分裂生
成物、ＤＢＰ、ＭＢＰを含む残留物、Ｎ ａ ＯＨ溶液
とに分離される。そして、分離されたＴＢＰは工程■で
再利用または廃棄系へ送られ、ＮａＯＨ溶液は工程＠の
廃液処理系へ送られる。The amount of residual substances such as TBP removed is approximately 20% in the neutralization cleaning process ■. The product is neutralized and washed with 1 NaOH solution, and is separated into TBP, a residue containing nuclear fuel material, fission products, DBP, and MBP, and an Na OH solution in step (1) and [phase]. Then, the separated TBP is sent to the reuse or disposal system in step ①, and the NaOH solution is sent to the waste liquid treatment system in step @.
なお、以上の説明においてはＴＢＰを例にとって説明し
たが、本発明による廃溶媒の処理方法は、ＴＢＰのみで
なく、溶媒抽出で使用されている他の種類の溶媒の分離
再生にも適用可能であることは明らかである。Although TBP was used as an example in the above explanation, the waste solvent treatment method according to the present invention is applicable not only to TBP but also to the separation and regeneration of other types of solvents used in solvent extraction. It is clear that there is.
以上のように本発明によれば、再処理工場、燃料工場等
の溶媒抽出工程から発生する廃？８液を凍結真空乾燥法
により、凝縮液、ＴＢＰ等残留物に大別し、凝縮液はさ
らに比重差によりｎ・ドデカン等の可燃性有機溶媒と硝
酸、水等に分離でき、ｎ・ドデカン等は再利用もしくは
ＴＢＰに起因するリン含有量が大幅に減ったため（１例
では百分の１）、焼却処理が容易になる。また、ＴＢＰ
等残留物は高濃度のＮａ０Ｈｉ８液で中和洗浄すること
により、核燃料物質、核分裂生成物、ＤＢＰ、ＭＢＰを
ＴＢＰより分離し再生することが可能となり、また高温
利用による腐食の問題を解消することができる。さらに
、ｎ・ドデカン等にリン、放射性核種の同伴が少ないた
め焼却処理が可能となるため凝縮液の処理が容易にする
ことができる。As described above, according to the present invention, waste generated from solvent extraction processes at reprocessing plants, fuel plants, etc. The 8 liquids are roughly divided into condensate and residues such as TBP by freeze-vacuum drying, and the condensate can be further separated into flammable organic solvents such as n-dodecane, nitric acid, water, etc. due to the difference in specific gravity, and n-dodecane, etc. The phosphorus content due to recycling or TBP has been significantly reduced (by 1/100 in one case), making it easier to incinerate. Also, TBP
By neutralizing and cleaning the residue with a high concentration Na0Hi8 solution, it becomes possible to separate and regenerate nuclear fuel material, fission products, DBP, and MBP from TBP, and also solve the problem of corrosion due to high temperature use. I can do it. Furthermore, since n-dodecane and the like contain less phosphorus and radioactive nuclides, incineration treatment becomes possible, making it easier to treat the condensate.
また、装置構成材料に腐食の問題が生じる高温を利用せ
ず、低温を利用し、腐食、火災、爆発の発生の恐れをな
くし、安全性を高くでき、腐食性で処分困難なリン酸等
の添加物を加えずにＴＢＰと水、硝酸、ｎ・ドデカン、
ＤＢＰＳＭＢＰ等を分離できると共に、水、硝酸、ｎ・
ドデカン等への放射性核種の同伴を少なくすることがで
きる。In addition, it uses low temperatures instead of high temperatures, which can cause problems of corrosion on the equipment's constituent materials, eliminating the risk of corrosion, fire, and explosions, increasing safety, and eliminating corrosive and difficult-to-dispose of phosphoric acid, etc. TBP and water, nitric acid, n-dodecane, without adding additives.
DBPSMBP, etc. can be separated, and water, nitric acid, n.
Entrainment of radionuclides into dodecane etc. can be reduced.
そして、ＴＢＰの再利用が可能となり、さらに処分する
ためのＴＢＰ等の固化物を作成する際にもＴＢＰ固化固
化体容入幅に小さくできる。Then, TBP can be reused, and when producing a solidified product such as TBP for disposal, the width can be reduced to the width of the TBP solidified product.
第１図は本発明の廃）容媒処理の全体構成を示す図、第
２図はプロセスフローを説明するための図である。
１・・・凍結乾燥器、２・・・廃溶媒、３・・・冷媒、
４・・・加熱媒体、５・・・凝縮器、６・・・真空ポン
プ、７・・・冷媒、８・・・凝縮液受槽、９・・・有機
相、１０・・・水相、１１・・・ｎドデカン及びケロシ
ン等、１２・・・水・硝酸等、１３・・・ＴＢＰ−核燃
料物質・核分裂生成物、■−・廃溶媒、■−冷媒、■−
加熱媒体、■−ＴＢＰ等残留物、■−中和洗浄工程、■
−１疑縮器および凝縮液、■−ｎ・ドデカン等、■−水
・硝酸等、■−Ｔ Ａ Ｐ 、＠’−−Ｎ ａ ＯＨ’
ｐ液、■−再利用又は廃棄系、＠−廃液処理系。FIG. 1 is a diagram showing the overall configuration of the waste container treatment of the present invention, and FIG. 2 is a diagram for explaining the process flow. 1... Freeze dryer, 2... Waste solvent, 3... Refrigerant,
4... Heating medium, 5... Condenser, 6... Vacuum pump, 7... Refrigerant, 8... Condensate receiver tank, 9... Organic phase, 10... Water phase, 11 ...n Dodecane and kerosene, etc., 12...Water, nitric acid, etc., 13...TBP-Nuclear fuel material/fission products, ■--Waste solvent, ■-Refrigerant, ■-
Heating medium, ■-TBP etc. residue, ■-neutralization cleaning process, ■
-1 pseudo-condenser and condensate, ■-n, dodecane, etc., ■-water, nitric acid, etc., ■-T A P, @'--N a OH'
p-liquid, ■-reuse or disposal system, @-waste treatment system.
Claims (5)
発生する放射性廃溶媒の処理方法において、凍結・昇華
工程、昇華した蒸発物質を凝縮分離する工程、昇華しな
い残留物を分離回収する工程を含むことを特徴とする廃
溶媒の処理方法。(1) In a method for treating radioactive waste solvents generated from solvent extraction processes at reprocessing plants, fuel manufacturing plants, etc., there is a freezing/sublimation process, a process of condensing and separating sublimated evaporated substances, and a process of separating and recovering non-sublimated residues. A method for treating a waste solvent, the method comprising:
・ドデカン等よりなる凝縮液と、ＴＢＰ、ＤＢＰ、ＭＢ
Ｐおよび蒸発しない核燃料物質、核分裂生成物を含む残
留物とに分離することを特徴とする請求項１記載の廃溶
媒の処理方法。(2) The freezing/sublimation process consists of nitric acid, water, sublimating nuclide, n
・Condensate consisting of dodecane, etc., TBP, DBP, MB
2. The method for treating waste solvent according to claim 1, wherein the waste solvent is separated into P and a residue containing non-evaporating nuclear fuel material and fission products.
等よりなる有機相に分離される請求項１記載の廃溶媒の
処理方法。(3) The method for treating waste solvent according to claim 1, wherein the condensate is separated into an aqueous phase consisting of nitric acid and water and an organic phase consisting of n-dodecane or the like.
浄工程からなる請求項１記載の廃溶媒の処理方法。(4) The method for treating waste solvent according to claim 1, wherein the step of separating and recovering the residue that does not sublimate comprises a neutralization washing step.
あり、ＴＢＰ等に同伴しているＤＢＰ、ＭＢＰ、核燃料
物質、核分裂物質等を分離する請求項１記載の廃溶媒の
処理方法。(5) The method for treating waste solvent according to claim 1, wherein the neutralization cleaning step is a cleaning step using a concentrated NaOH solution, and DBP, MBP, nuclear fuel material, fissile material, etc. accompanying TBP etc. are separated.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63142398A JPH01311296A (en) | 1988-06-09 | 1988-06-09 | Processing method for waste solvent |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63142398A JPH01311296A (en) | 1988-06-09 | 1988-06-09 | Processing method for waste solvent |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01311296A true JPH01311296A (en) | 1989-12-15 |
Family
ID=15314426
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63142398A Pending JPH01311296A (en) | 1988-06-09 | 1988-06-09 | Processing method for waste solvent |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01311296A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114956295A (en) * | 2022-04-24 | 2022-08-30 | 中国核电工程有限公司 | Radioactive waste TBP kerosene suspension and preparation method thereof |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5423900A (en) * | 1977-07-25 | 1979-02-22 | Mitsubishi Metal Corp | Recovering regeneration method of radioactive retreating waste organic solvent |
| JPS6227697A (en) * | 1985-07-29 | 1987-02-05 | 動力炉・核燃料開発事業団 | Method and device for processing waste liquor containing radioactive substance |
| JPS6249296A (en) * | 1985-08-28 | 1987-03-03 | 株式会社東芝 | Evaporating concentrator |
| JPS62200298A (en) * | 1986-02-27 | 1987-09-03 | 株式会社日立製作所 | Method and device for washing organic solvent |
-
1988
- 1988-06-09 JP JP63142398A patent/JPH01311296A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5423900A (en) * | 1977-07-25 | 1979-02-22 | Mitsubishi Metal Corp | Recovering regeneration method of radioactive retreating waste organic solvent |
| JPS6227697A (en) * | 1985-07-29 | 1987-02-05 | 動力炉・核燃料開発事業団 | Method and device for processing waste liquor containing radioactive substance |
| JPS6249296A (en) * | 1985-08-28 | 1987-03-03 | 株式会社東芝 | Evaporating concentrator |
| JPS62200298A (en) * | 1986-02-27 | 1987-09-03 | 株式会社日立製作所 | Method and device for washing organic solvent |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114956295A (en) * | 2022-04-24 | 2022-08-30 | 中国核电工程有限公司 | Radioactive waste TBP kerosene suspension and preparation method thereof |
| CN114956295B (en) * | 2022-04-24 | 2024-01-23 | 中国核电工程有限公司 | A radioactive waste TBP kerosene suspension and its preparation method |
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