JPH083556B2 - Radioactive waste liquid treatment device - Google Patents
Radioactive waste liquid treatment deviceInfo
- Publication number
- JPH083556B2 JPH083556B2 JP17427287A JP17427287A JPH083556B2 JP H083556 B2 JPH083556 B2 JP H083556B2 JP 17427287 A JP17427287 A JP 17427287A JP 17427287 A JP17427287 A JP 17427287A JP H083556 B2 JPH083556 B2 JP H083556B2
- Authority
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- Japan
- Prior art keywords
- extractant
- solvent
- tank
- liquid
- capturing
- 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 - Lifetime
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Description
【発明の詳細な説明】 [産業上の利用分野] 本発明は、核燃料サイクルで生じる超ウラン元素(ア
クチナイド系元素)を含む廃液から超ウラン元素の抽出
分離を行う放射性廃液処理装置に関するものである。Description: TECHNICAL FIELD The present invention relates to a radioactive liquid waste treatment apparatus for extracting and separating transuranic element from a waste liquid containing transuranic element (actinide element) generated in a nuclear fuel cycle. .
[従来の技術] 原子炉設備に於いて核燃料を燃焼させると核燃料が消
耗して核分裂生成物を生じると共にプルトニュウム239P
u等が生じる。このプルトニュウム等は核分裂核種であ
って、抽出精製することにより、再び核燃料として使用
可能である。従って、使用済核燃料を再処理することが
行われる。これを核燃料サイクルというが、使用済核燃
料の再処理の過程で放射性廃液を生じる。この放射性廃
液の中には239Pu以外の長半減期の超ウラン元素(237N
p、241Am等)や核分裂生成物(90Sr、99Tc、137Cs等)
が含まれている。このためこれらの核種を分離し、核種
の特性に応じた処理を行ない廃棄物処理処分時の安全性
向上や、放射性同位体資源としての有効利用を図る必要
があり、放射性廃液の処理の1に超ウラン元素の回収が
行われる。[Prior Art] When nuclear fuel is burned in a nuclear reactor facility, the nuclear fuel is exhausted to produce fission products and plutonium 239 P
u etc. occurs. The plutonium and the like are fission nuclides and can be reused as nuclear fuel by extracting and refining. Therefore, the spent nuclear fuel is reprocessed. This is called the nuclear fuel cycle, and radioactive waste liquid is generated in the process of reprocessing spent nuclear fuel. This radioactive liquid waste contains a long half-life transuranic element ( 237 N) other than 239 Pu.
p, 241 Am, etc.) and fission products ( 90 Sr, 99 Tc, 137 Cs, etc.)
It is included. For this reason, it is necessary to separate these nuclides and perform treatment according to the characteristics of the nuclide to improve the safety at the time of waste treatment and disposal, and to make effective use as a radioactive isotope resource. Transuranic elements are recovered.
従来より、該超ラウン元素の抽出には抽出剤(DHDECM
P:ジヘキシ−N−Nジエチルカルバモイルメチレンホス
ホネート、TBP:トリブチルホスホネート等)が用いられ
ている。従来の、抽出剤による超ウラン元素抽出方法と
しては、廃液中に抽出剤を入れて撹拌し、超ウラン元素
のみを抽出剤中に取込み、先ず水と抽出剤とを分離し、
次に抽出剤と抽出剤中の超ウラン元素とを分離するいわ
ゆる液々抽出法と呼ばれているものでミキサーセトラー
等が使われる。Conventionally, the extraction agent (DHDECM
P: dihex-NN diethylcarbamoylmethylene phosphonate, TBP: tributylphosphonate, etc. are used. As a conventional transuranic element extraction method using an extractant, the extractant is put into a waste liquid and stirred, and only the transuranic element is taken into the extractant, and water and the extractant are first separated,
Next, a so-called liquid extraction method for separating the extractant and the transuranium element in the extractant is a so-called liquid extraction method, and a mixer settler or the like is used.
[発明が解決しようとする問題点] 然し、上記した従来の方法では撹拌の為には抽出剤が
大量に必要であり、撹拌後、抽出剤と水との分離を完全
に行うことができないので、抽出剤が分離した水のに混
入して抽出されてしまう、抽出剤の損失が大きい。[Problems to be Solved by the Invention] However, in the above-mentioned conventional method, a large amount of extractant is required for stirring, and the extractant and water cannot be completely separated after stirring. However, the extractant is mixed with the separated water and extracted, and the loss of the extractant is large.
ところが、抽出剤自体はDHDECMPの場合大体1500円/g
と非常に高価なものであって、大量の廃液を処理しよう
とすると、その処理コストは極めて高価なものとなって
しまう。However, in the case of DHD ECMP, the extractant itself is about 1500 yen / g
It is very expensive, and if a large amount of waste liquid is to be treated, the treatment cost will be extremely high.
[問題点を解決するための手段] 本発明は上記実情を鑑み、少量の抽出剤で効率よく且
抽出剤の損失ロスの極めて少ない放射性廃液処理装置を
提供とするものであって、抽出剤と乳化用液とを混合し
てエマルジョン化する超音波槽と、 該超音波槽でエマルジョン化された抽出剤と原子力燃料
処理廃液とを撹拌する撹拌・抽出槽と、 該撹拌・抽出槽で撹拌された撹拌混合液が送給ライン
を介して送給され且つ抽出剤を吸着捕捉する多孔質物が
充填された抽出剤捕捉塔と、 抽出剤より超ウラン元素を溶離する溶離液を前記抽出
剤捕捉塔へ供給する溶離液槽と、 前記抽出剤捕捉塔において抽出剤より超ウラン元素が
溶離された溶離液を回収する元素回収液排出ラインと、 前記抽出剤捕捉塔において捕捉された抽出剤を溶解さ
せる為の溶媒を溶媒供給ラインを介して前記抽出剤捕捉
塔へ供給する溶媒槽と、 抽出剤を溶解した溶媒が前記抽出剤捕捉塔から送給さ
れ、溶媒を蒸発せしめて抽出剤を分離回収し且つ該抽出
剤を前記超音波槽へ戻す溶媒蒸発器と、 該溶媒蒸発器からの溶媒を凝縮せしめて前記溶媒槽へ
戻す凝縮器と を備えたことを特徴とするものである。[Means for Solving the Problems] In view of the above circumstances, the present invention provides a radioactive waste liquid treatment apparatus that efficiently uses a small amount of extractant and has extremely small loss loss of the extractant. An ultrasonic bath that mixes an emulsifying liquid to make an emulsion, a stirring / extracting tank that stirs the extractant emulsified in the ultrasonic bath and the nuclear fuel processing waste liquid, and agitating in the stirring / extracting tank. The agitated mixed solution is fed through the feed line and the extractant-capturing tower filled with the porous material that adsorbs and captures the extractant, and the eluent that elutes the transuranium element from the extractant are the extractant-capture tower. An eluent tank for supplying the eluent, an element recovery liquid discharge line for recovering an eluent in which the transuranium element is eluted from the extractant in the extractant trap, and an extractant trapped in the extractant trap Solvent for A solvent tank for supplying the extractant to the extractant-capturing tower through a supply line, and a solvent in which the extractant is dissolved are fed from the extractant-captured tower to evaporate the solvent to separate and recover the extractant and extract the extractant. A solvent evaporator for returning to the ultrasonic tank, and a condenser for condensing the solvent from the solvent evaporator and returning it to the solvent tank are provided.
[作用] エマルジョン化した抽出剤と廃液との混合撹拌によ
り、抽出剤により廃液中の超ウラン元素の抽出が行わ
れ、更に、混合液を抽出剤捕捉塔を通過させることによ
り、抽出剤は多孔質物に吸着捕捉され廃液からの超ウラ
ン元素分離が行われる。次に、溶離液を通すことによ
り、超ウラン元素が抽出剤より溶離されて取出される。
抽出剤は、溶媒によって溶解され、抽出剤捕捉塔より取
出された後溶媒と分離され、抽出剤及び溶媒はそれぞれ
回収され再使用される。[Operation] By mixing and stirring the emulsified extractant and the waste liquid, the transuranic element in the waste liquid is extracted by the extractant, and further, the mixed liquid is passed through the extractant-capturing tower so that the extractant is porous. The transuranic element is separated from the waste liquid by being adsorbed and captured by the substance. Next, the transuranic element is eluted and extracted from the extractant by passing an eluent.
The extractant is dissolved in the solvent, taken out from the extractant trap tower, and then separated from the solvent, and the extractant and the solvent are respectively recovered and reused.
[実 施 例] 以下図面を参照しつつ本発明の1実施例を説明する。[Example] An example of the present invention will be described below with reference to the drawings.
1は超音波槽であって、該超音波槽1には抽出剤補給
ライン2、乳化用液(水)供給ライン3が接続されてい
る。An ultrasonic tank 1 is connected to an extractant supply line 2 and an emulsifying liquid (water) supply line 3 to the ultrasonic tank 1.
4は撹拌・抽出槽であって、該撹拌・抽出槽4には廃
液供給ライン5が接続され、該廃液供給ライン5の途中
にラインミキサ6を設け、又廃液供給ライン5のライン
ミキサ6の上流側に前記超音波槽1からの送出ライン7
を接続する。該送出ライン7の途中には送出ポンプ8を
設ける。Reference numeral 4 denotes a stirring / extracting tank, a waste liquid supply line 5 is connected to the stirring / extracting tank 4, a line mixer 6 is provided in the middle of the waste liquid supply line 5, and a line mixer 6 of the waste liquid supply line 5 is provided. Delivery line 7 from the ultrasonic tank 1 on the upstream side
Connect. A delivery pump 8 is provided in the middle of the delivery line 7.
途中に送給ポンプ9を有する送給ライン10は撹拌・抽
出槽4、抽出剤捕捉塔11とを接続する。該抽出剤捕捉塔
11は内部に非極性イオン交換樹脂製多孔質物を充填して
ある。この非極性イオン交換樹脂としてはポリスチレン
−DVB樹脂、テトラフルオロエチレン樹脂等が挙げられ
る。A feeding line 10 having a feeding pump 9 on the way connects the stirring / extracting tank 4 and the extractant capturing tower 11. The extractant capturing tower
No. 11 is filled with a non-polar ion-exchange resin porous material inside. Examples of the non-polar ion exchange resin include polystyrene-DVB resin and tetrafluoroethylene resin.
抽出剤捕捉塔11と前記超音波槽1とを抽出剤循環ライ
ン12により接続し、該循環ライン12に抽出剤捕捉塔11側
より抽出剤脱離溶媒受槽13、循環ポンプ14、溶媒蒸発器
15、回収抽出剤受槽16を順次設ける。溶媒蒸発器15を溶
媒循環ライン17により溶媒槽18に接続し、該溶媒循環ラ
イン17に前記蒸発器15側より凝縮器19、回収溶媒受槽20
を設ける。The extractant capturing tower 11 and the ultrasonic tank 1 are connected by an extractant circulating line 12, and the extractant desorbing solvent receiving tank 13, circulation pump 14, solvent evaporator from the extractant capturing tower 11 side to the circulating line 12.
15, the recovery extractant receiving tank 16 is provided in sequence. The solvent evaporator 15 is connected to a solvent tank 18 by a solvent circulation line 17, and a condenser 19 and a recovered solvent receiving tank 20 are connected to the solvent circulation line 17 from the evaporator 15 side.
To provide.
前記溶媒槽18と抽出剤捕捉塔11とは溶媒供給ライン21
により送給ポンプ22を介して接続してある。又、抽出剤
捕捉塔11には溶離液槽27が、送給ポンプ23を介して接続
されると共に処理液排出ライン24、元素回収液排出ライ
ン26が接続される。The solvent tank 18 and the extractant capturing tower 11 are provided with a solvent supply line 21.
Are connected via the feed pump 22. Further, an eluent tank 27 is connected to the extractant capturing tower 11 via a feed pump 23, and a treatment liquid discharge line 24 and an element recovery liquid discharge line 26 are also connected.
26は乾燥ラインであって、抽出剤捕捉塔11からの排気
は前記凝縮器15に導かれた後排気される。Reference numeral 26 denotes a drying line, and the exhaust gas from the extractant capturing tower 11 is guided to the condenser 15 and then exhausted.
以下作用について説明する。 The operation will be described below.
超音波槽1内には抽出剤と乳化用液(水)がそれぞれ
抽出剤補給ライン2、乳化用液供給ライン3を経て貯溜
されている。超音波槽1では超音波による振動で抽出剤
と水とが混合されエマルジョン化されて乳化液となる。
このエマルジョン化により、抽出剤は微粒となり、その
表面積は格段に増大する。乳化液は送出ポンプ8によっ
て廃液供給ライン5に投入され、ラインミキサ6によっ
て乳化液とが混合され、混合液は撹拌・抽出槽4に送出
される。An extractant and an emulsifying liquid (water) are stored in the ultrasonic tank 1 via an extractant replenishing line 2 and an emulsifying liquid supply line 3, respectively. In the ultrasonic tank 1, the extractant and water are mixed by the vibration of ultrasonic waves to be emulsified and become an emulsion.
By this emulsification, the extractant becomes fine particles and the surface area thereof is remarkably increased. The emulsified liquid is introduced into the waste liquid supply line 5 by the delivery pump 8, mixed with the emulsified liquid by the line mixer 6, and the mixed liquid is delivered to the stirring / extraction tank 4.
撹拌・抽出槽4では更に乳化液と廃液との撹拌、即ち
抽出剤の微粒と廃液との接触が行われ、抽出剤による廃
液中の超ウラン元素の抽出が行われる。In the stirring / extracting tank 4, the emulsified liquid and the waste liquid are further stirred, that is, the fine particles of the extractant are contacted with the waste liquid, and the transuranic element in the waste liquid is extracted by the extractant.
撹拌・抽出槽4での抽出が行われた後、混合液は送出
ポンプ9により送給ライン10を経て抽出剤捕捉塔11に送
出される。混合液は該抽出剤捕捉塔11内の多孔質物層を
通って処理液排出ライン24より貯溜タンク(図示せず)
へ送られる。この混合液の多孔質送通過過程で、多孔質
物層に抽出剤が吸着捕捉され、前記処理液排出ライン24
より排出される液は抽出剤の微粒(即ち超ウラン元素)
が取除かれたものとなる。After the extraction in the stirring / extracting tank 4, the mixed liquid is delivered to the extractant capturing tower 11 via the delivery line 10 by the delivery pump 9. The mixed liquid passes through the porous material layer in the extractant trap tower 11 and is discharged from the processing liquid discharge line 24 to a storage tank (not shown).
Sent to. During the process of porous passage of this mixed liquid, the extractant is adsorbed and captured in the porous material layer, and the treated liquid discharge line 24
The liquid discharged is fine particles of extractant (ie transuranic element)
Will have been removed.
多孔質物が抽出剤を捕捉すると着色するので、抽出剤
捕捉塔11を透明の容器にすると抽出剤の捕捉状態を目視
によって確認することができる。Since the porous material is colored when it captures the extractant, if the extractant trap tower 11 is a transparent container, the trapped state of the extractant can be visually confirmed.
抽出剤捕捉塔11による抽出剤の捕捉が飽和状態となる
送出ポンプ9による混合液の送出を停止し、送給ポンプ
23により溶離液を抽出剤捕捉塔11内に差込む。溶離液は
抽出剤が抽出した超ウラン元素を溶離して元素回収液排
出ライン25より、超ウラン元素分離設備(図示せず)へ
送られる。When the extractant capturing tower 11 captures the extractant in a saturated state, the delivery pump 9 stops the delivery of the mixed liquid, and the delivery pump
By 23, the eluent is inserted into the extractant trap tower 11. The eluent elutes the transuranium element extracted by the extractant and is sent from the element recovery liquid discharge line 25 to a transuranic element separation facility (not shown).
溶離液による超ウラン元素の溶離が終ると、多孔質物
に捕捉されているものは抽出剤だけとなるが、この抽出
剤はアセトン等の有機溶媒により解かして回収する。After the elution of the transuranium element with the eluent, only the extractant is trapped in the porous material, and this extractant is recovered by being thawed with an organic solvent such as acetone.
供給ポンプ22により、溶媒槽18より溶媒を抽出剤捕捉
剤11内を通過させて抽出剤を溶解させる。抽出剤の溶解
の状態はやはり多孔質物の色の変化で確認することがで
きる。抽出剤を溶解した溶媒は一旦抽出剤脱離溶媒受槽
13に貯溜され、更に循環ポンプ14で流量をコントロール
されて蒸発器15へ送られる。The supply pump 22 allows the solvent to pass through the extractant-capturing agent 11 from the solvent tank 18 to dissolve the extractant. The dissolution state of the extractant can be confirmed by the change in the color of the porous material. The solvent in which the extractant is dissolved is once the solvent for removing the extractant solvent
It is stored in 13 and is sent to the evaporator 15 with the flow rate controlled by the circulation pump 14.
蒸発器15では、溶媒が蒸発されて、その蒸気は凝縮器
19へ送られ、凝縮器19で液化され、回収溶媒受槽20で受
けられ、更に溶媒循環ライン17を経て、溶媒槽18へ貯溜
される。In the evaporator 15, the solvent is evaporated and the vapor is condensed.
It is sent to 19, is liquefied in the condenser 19, is received in the recovered solvent receiving tank 20, and is further stored in the solvent tank 18 via the solvent circulation line 17.
前記蒸発器15で分離された回収抽出剤は受槽16で受け
られ、更に必要に応じて前記超音波槽1へ供給される。The recovered extractant separated by the evaporator 15 is received by the receiving tank 16, and is further supplied to the ultrasonic tank 1 as required.
以上の如くして、抽出剤と溶媒の回収が行われる。 The extractant and the solvent are recovered as described above.
多孔質物に捕捉された抽出剤が溶媒により取除かれる
と、多孔質物の乾燥を行う。多孔質物の乾燥ライン26よ
り乾燥空気を送込むことによって行われ、多孔質物に付
着した溶媒を蒸発乾燥させる。抽出剤捕捉等11より排気
された乾燥用空気は凝縮器19へ導びかれ、気化溶媒を除
去した後排出される。When the extractant trapped in the porous material is removed by the solvent, the porous material is dried. This is performed by sending dry air from the drying line 26 for the porous material to evaporate and dry the solvent attached to the porous material. The drying air exhausted from the extractant trapping 11 or the like is guided to the condenser 19, and is removed after removing the vaporized solvent.
多孔質物の乾燥が終ると、再び前記した一連の工程が
繰返えされて、超ウラン元素の分離が行われる。When the drying of the porous material is completed, the series of steps described above is repeated again to separate the transuranic element.
[発明の効果] 以上述べた如く本発明によれば、抽出剤をエマルジョ
ン化して廃液と撹拌するので抽出剤と廃液との接触面積
が大きく、少量の抽出剤で廃液中の超ウラン元素を効果
的に抽出することができる。又、抽出剤は回収循環され
るシステムとなっており損失は極めて少ない。[Effects of the Invention] As described above, according to the present invention, since the extractant is emulsified and stirred with the waste liquid, the contact area between the extractant and the waste liquid is large, and the transuranic element in the waste liquid is effective with a small amount of the extractant. Can be extracted. In addition, the extractant is a system in which it is collected and circulated, and the loss is extremely small.
図は本発明の概念を示すブロック図である。 1は超音波槽、4は撹拌・抽出槽、10は送給ライン、11
は抽出剤捕捉塔、12は抽出剤循環ライン、15は溶媒蒸発
器、17は溶媒循環ライン、18は溶媒槽、19は凝縮器、21
は溶媒供給ライン、27は溶媒液槽を示す。The figure is a block diagram showing the concept of the present invention. 1 is an ultrasonic tank, 4 is a stirring / extracting tank, 10 is a feeding line, 11
Is an extractant capture tower, 12 is an extractant circulation line, 15 is a solvent evaporator, 17 is a solvent circulation line, 18 is a solvent tank, 19 is a condenser, 21
Is a solvent supply line, and 27 is a solvent liquid tank.
Claims (1)
ン化する超音波槽と、 該超音波槽でエマルジョン化された抽出剤と原子力燃料
処理廃液とを撹拌する撹拌・抽出槽と、 該撹拌・抽出槽で撹拌された撹拌混合液が送給ラインを
介して送給され且つ抽出剤を吸着捕捉する多孔質物が充
填された抽出剤捕捉塔と、 抽出剤より超ウラン元素を溶離する溶離液を前記抽出剤
捕捉塔へ供給する溶離液槽と、 前記抽出剤捕捉塔において抽出剤より超ウラン元素が溶
離された溶離液を回収する元素回収液排出ラインと、 前記抽出剤捕捉塔において捕捉された抽出剤を溶解させ
る為の溶媒を溶媒供給ラインを介して前記抽出剤捕捉塔
へ供給する溶媒槽と、 抽出剤を溶解した溶媒が前記抽出剤捕捉塔から送給さ
れ、溶媒を蒸発せしめて抽出剤を分離回収し且つ該抽出
剤を前記超音波槽へ戻す溶媒蒸発器と、 該溶媒蒸発器からの溶媒を凝縮せしめて前記溶媒槽へ戻
す凝縮器と を備えたことを特徴とする放射性廃液処理装置。1. An ultrasonic tank for mixing an extractant and an emulsifying liquid to form an emulsion, and a stirring / extracting tank for stirring the extractant emulsified in the ultrasonic tank and a nuclear fuel processing waste liquid. An extractant-capturing tower filled with a porous material for adsorbing and capturing the extractant, in which an agitated mixed solution stirred in the agitating / extracting tank is fed through a feed line, and a transuranium element is eluted from the extractant An eluent tank for supplying an eluent to the extractant-capturing tower, an element recovery liquid discharge line for recovering an eluent in which the transuranium element is eluted from the extractant in the extractant-capturing tower, and an extractant-capturing tower A solvent tank for supplying a solvent for dissolving the captured extractant to the extractant capturing tower through a solvent supply line, and a solvent in which the extractant is dissolved are sent from the extractant capturing tower to evaporate the solvent. At least separate the extractant and collect it And a solvent evaporator to return the extractant to the ultrasonic bath, the radioactive liquid waste treatment apparatus characterized by comprising a condenser back to the solvent tank allowed condense solvent from the solvent evaporator.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP17427287A JPH083556B2 (en) | 1987-07-13 | 1987-07-13 | Radioactive waste liquid treatment device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP17427287A JPH083556B2 (en) | 1987-07-13 | 1987-07-13 | Radioactive waste liquid treatment device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6418096A JPS6418096A (en) | 1989-01-20 |
| JPH083556B2 true JPH083556B2 (en) | 1996-01-17 |
Family
ID=15975753
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP17427287A Expired - Lifetime JPH083556B2 (en) | 1987-07-13 | 1987-07-13 | Radioactive waste liquid treatment device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH083556B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2001321603A (en) * | 2000-05-17 | 2001-11-20 | Satoru Yoshinaka | Method and device for treating dioxins |
| KR100371680B1 (en) * | 2000-08-18 | 2003-02-11 | 한국지질자원연구원 | Method for long term and continuos operation of supported liquid membrane by periodical supply of extraction reagent |
-
1987
- 1987-07-13 JP JP17427287A patent/JPH083556B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6418096A (en) | 1989-01-20 |
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