JPH0313896A - Radioactive waste liquid disposal facility - Google Patents
Radioactive waste liquid disposal facilityInfo
- Publication number
- JPH0313896A JPH0313896A JP14668789A JP14668789A JPH0313896A JP H0313896 A JPH0313896 A JP H0313896A JP 14668789 A JP14668789 A JP 14668789A JP 14668789 A JP14668789 A JP 14668789A JP H0313896 A JPH0313896 A JP H0313896A
- Authority
- JP
- Japan
- Prior art keywords
- tank
- waste liquid
- radioactive waste
- membrane
- pump
- 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
- 239000007788 liquid Substances 0.000 title claims abstract description 63
- 239000002901 radioactive waste Substances 0.000 title claims description 35
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 61
- 239000012153 distilled water Substances 0.000 claims abstract description 21
- 238000011144 upstream manufacturing Methods 0.000 claims abstract description 6
- 239000012528 membrane Substances 0.000 claims description 55
- 230000002209 hydrophobic effect Effects 0.000 claims description 15
- 238000004821 distillation Methods 0.000 claims description 5
- 238000011084 recovery Methods 0.000 claims description 3
- 238000000034 method Methods 0.000 claims 1
- 238000005115 demineralization Methods 0.000 abstract description 4
- 230000002328 demineralizing effect Effects 0.000 abstract description 4
- 230000005855 radiation Effects 0.000 abstract description 2
- 239000002699 waste material Substances 0.000 abstract 3
- 239000007789 gas Substances 0.000 description 7
- 230000008023 solidification Effects 0.000 description 6
- 238000007711 solidification Methods 0.000 description 6
- 239000000498 cooling water Substances 0.000 description 4
- 238000010612 desalination reaction Methods 0.000 description 4
- 239000007787 solid Substances 0.000 description 3
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 229910052796 boron Inorganic materials 0.000 description 2
- 238000009833 condensation Methods 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 239000012466 permeate Substances 0.000 description 2
- 238000000926 separation method Methods 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 239000010426 asphalt Substances 0.000 description 1
- 238000011001 backwashing Methods 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 1
- 239000004327 boric acid Substances 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 229920000642 polymer Polymers 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000005406 washing Methods 0.000 description 1
Landscapes
- Separation Using Semi-Permeable Membranes (AREA)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は原子力発電所等に通用される放射性廃液処理装
置に係るものである。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a radioactive waste liquid treatment device commonly used in nuclear power plants and the like.
（従来の技術）
従来、原子力発電所から発生する放射性廃液は、蒸発器
によって濃縮処理し、蒸留液を脱塩塔へ送って浄化した
後系外へ放出する一方、ａ槽液をセメント固化、アスフ
ァルト固化、ポリマー固化等によって処理している。(Prior art) Conventionally, radioactive waste liquid generated from nuclear power plants is concentrated using an evaporator, and the distilled liquid is sent to a desalination tower to be purified and then released outside the system. It is treated by asphalt solidification, polymer solidification, etc.
（発明が解決しようとする課題）
膜蒸留式の放射性廃液処理装置によって水蒸気の分離処
理を行なう場合、濃縮液側の濃度が高くなるのに伴って
透過水側へ溶質成分等が蒸気と同伴して透過する割合が
高くなる。(Problem to be Solved by the Invention) When water vapor is separated using a membrane distillation type radioactive waste liquid treatment device, as the concentration on the concentrated liquid side increases, solute components etc. are entrained with the vapor into the permeated water side. The rate of transmission increases.
このため高ａ縮時は、液濃度が低いときに比して、得ら
れる透過水中の不純物が多くなり、水質が悪くなるとい
う問題点がある。Therefore, when the a-condensation is high, there is a problem that the obtained permeated water contains more impurities than when the liquid concentration is low, and the water quality deteriorates.
本発明は前記従来技術の有する問題点に鑑みて提案され
たもので、その目的とする処は、放射液処理装置より得
られる透過水の水質は常時所定条件を満足し、且つ処理
液を目標濃度まで高ａｍすることができる放射性廃液処
理装置を提供する点にある。The present invention has been proposed in view of the problems of the prior art, and its purpose is to ensure that the quality of permeated water obtained from a radiation liquid treatment device always satisfies predetermined conditions, and that the treated liquid The object of the present invention is to provide a radioactive waste liquid treatment device capable of increasing the concentration of am.
（課題を解決するための手段）
前記の目的を達成するため、本発明に係る放射性廃液処
理装置は、タンクとポンプと膜蒸留器との間に放射性廃
液を循環させて濃縮液を得る放射性廃液？ａ縮千手段、
前記膜蒸留器により分離した水ｆ気を凝縮器によって凝
縮させる蒸留水回収手段とを具えた膜蒸留式の放射性廃
液処理装置において、前記濃縮液の濃度が一定値を超え
た時点、または蒸留水の水質が一定値に達した時点以後
、得られた蒸留水を上流側へ循環する循環手段を具備し
て構成されている。(Means for Solving the Problems) In order to achieve the above object, the radioactive waste liquid treatment device according to the present invention circulates the radioactive waste liquid between a tank, a pump, and a membrane distiller to obtain a concentrated liquid. ? a thousand means,
In a membrane distillation type radioactive waste liquid treatment apparatus comprising distilled water recovery means for condensing the water vapor separated by the membrane distiller using a condenser, when the concentration of the concentrated liquid exceeds a certain value, or when the distilled water After the water quality reaches a certain value, the distilled water is circulated to the upstream side.
本発明に係る放射性廃液処理装置においては、前記膜蒸
留器として疏水性均質膜の膜蒸留器を使用するものであ
る。In the radioactive waste liquid treatment apparatus according to the present invention, a membrane distiller having a hydrophobic homogeneous membrane is used as the membrane distiller.
（作用）
本発明に係る放射性廃液処理装置において、原水タンク
及びポンプ並に膜蒸留器との間に放射性廃液をＷｉ環さ
せるように構成された前記放射性廃液濃縮手段で得られ
た濃縮液の濃度が、所定値（例えばボロン濃度１０．０
００ｐｐｍ）を上回ると、膜蒸留器によって分離された
蒸留水の水質が所定の条件（ボロン濃度１０ｐｐｍ以下
）を満足しなくなるが、このとき得られた蒸留水を、前
記ｉｎ手段を介して上流側のタンクに戻すことによって
、本装置から下流へ放出する蒸留水の水質は常に所定の
条件を満足させることとなる。(Function) In the radioactive waste liquid treatment apparatus according to the present invention, the concentration of the concentrated liquid obtained by the radioactive waste liquid concentrating means configured to circulate the radioactive waste liquid between the raw water tank, the pump, and the membrane distiller. is a predetermined value (for example, boron concentration 10.0
00 ppm), the quality of the distilled water separated by the membrane distiller no longer satisfies the predetermined condition (boron concentration 10 ppm or less), but the distilled water obtained at this time is passed through the in means to the upstream side. By returning the distilled water to the tank, the quality of the distilled water discharged downstream from the device always satisfies predetermined conditions.
また処理液の供給を止めて、濃度運転を行なうことによ
り、目標濃度までの高濃度が可能となる。Further, by stopping the supply of the processing liquid and performing concentration operation, it is possible to achieve a high concentration up to the target concentration.
本発明においては前記膜蒸留器として、水蒸気以外のガ
ス分を透過しない疏水性均Ｉｌｌりを用いた膜蒸留器を
採用し、たことによって、蒸発に（トなう放射性物質の
キＡ・リーオーバがなくなり、また運転中、膜の２次側
（透過水側）の負圧を保持するための真空ポンプの稼動
率の低減が図られる。In the present invention, a membrane distiller using a hydrophobic homogenizer which does not permeate gas components other than water vapor is used as the membrane distiller. Also, during operation, the operating rate of the vacuum pump for maintaining negative pressure on the secondary side (permeated water side) of the membrane can be reduced.
（実施例）
次に本発明に係る放射性廃液処理装置を第１図に示す実
施例について説明する。(Example) Next, an example of a radioactive waste liquid treatment apparatus according to the present invention shown in FIG. 1 will be described.
（１）が原水タンク、（２）が原水ポンプ、（３）がタ
ンク（循環タンク） 、（／ｌ）がレベル計、（５）が
ポンプ（Ｗ１環ポンプ）、（６）がフィルり、（力がヒ
ータ、（８）がａ蒸留器、（９）が濃縮液管路、００）
が三方弁で、原水タンク（１）内の放射性廃液を原水ポ
ンプ（２）を経てタンク（循環タンク）（３）へ供給す
るように、またタンク（循環タンク）（３）内の放射性
廃液をポンプ（循環ポンプ）（５）→フィルタ（６）→
ヒータ（７）→膜蒸留器（８）→４ ’ＣＭ ？＆ 管
路（９） →三方弁（１０）−タフ ’ｙ （ｉ環タン
ク）（３）にｗｉ環するようになっている。(1) is the raw water tank, (2) is the raw water pump, (3) is the tank (circulation tank), (/l) is the level meter, (5) is the pump (W1 ring pump), (6) is the fill, (Power is the heater, (8) is the distiller a, (9) is the concentrate pipe, 00)
is a three-way valve, so that the radioactive waste liquid in the raw water tank (1) is supplied to the tank (circulation tank) (3) via the raw water pump (2), and the radioactive waste liquid in the tank (circulation tank) (3) is Pump (circulation pump) (5) → Filter (6) →
Heater (7) → Membrane distiller (8) → 4'CM? & Pipe line (9) → Three-way valve (10) - Tough 'y (I ring tank) It is designed to be connected to (3).
また前記膜蒸留器（８）は疏水性均質膜の片側に供給し
た放射性廃液（例えばほう酸（ＩｈＢ（ｈ）＋放射性物
質）から水（１１□０）のみを透過、蒸発させて、放射
性廃液中を濃１宿するように構成され°ζいる。このと
き、疏水性均質膜の透過水側（二次側）を水の透過、蒸
発を促進するために、負圧（約１１００ａｕｎｌ１以下
）に保持する。また図中（１１）が凝縮器、０りが前記
膜蒸留器（８）と同凝縮器（１１）とを連結する水蒸気
管路、θつが同水蒸気管路０２）に接続された逆洗空気
管路、０弔が前記凝縮器（１０に設けた冷却水管路、０
５１が同凝縮器（１１）の側部に接続した真空ポンプ、
００が同凝縮器（Ｉｔ）の底部・に接続した脱塩塔ポン
プ、０７）が同脱塩塔ポンプＯωに接続した脱塩塔（膜
蒸留器（８）のバックアップ機器）、θ８）が前記三方
弁００）に接続し７た固化装置、（１９）が固化体であ
る。Further, the membrane distiller (8) permeates and evaporates only water (11□0) from the radioactive waste liquid (for example, boric acid (IhB(h) + radioactive substance) supplied to one side of the hydrophobic homogeneous membrane, and evaporates it into the radioactive waste liquid. At this time, the permeated water side (secondary side) of the hydrophobic homogeneous membrane is maintained at negative pressure (approximately 1100 aunl or less) to promote water permeation and evaporation. In the figure, (11) is the condenser, 0 is the steam pipe connecting the membrane distiller (8) and the condenser (11), and θ is the reverse water vapor pipe connected to the same steam pipe 02). The air washing pipe line 0 is the cooling water pipe provided in the condenser (10).
51 is a vacuum pump connected to the side of the condenser (11),
00 is the demineralization tower pump connected to the bottom of the condenser (It), 07) is the demineralization tower (backup equipment for the membrane distiller (8)) connected to the demineralization tower pump Oω, and θ8) is the The solidification device (19) connected to the three-way valve 00) is the solidified body.
次に前記放射性廃液処理装置の作用を具体的に説明する
。Next, the operation of the radioactive waste liquid treatment device will be specifically explained.
原水タンク（１）内の放射性廃液を原水ポンプ（２）に
よりタンク＜Ｖ＆ｍタンク）（３）内へ送り、次いで同
タンク（循環タンク）（３）内の放射性廃液をポンプ（
膜蒸留ポンプ）（５）によりフィルタ（６）へ送り、こ
こで放射性廃液中の懸濁物質を除去し、次いでヒータ（
７）へ送り、ここで７０〜９５°Ｃ程度に加熱し１次い
で膜蒸留器（８）へ送り、ここで放射性廃液を水茎気と
４縮液とに分離する。即ち、同）膜蒸留器（８）におけ
る疏水性均質膜の片側に供給した放射性廃液（例えばほ
う酸（ＩＩＪ（１＋）＋放射性物質）から水（１１２０
）のみを透過、蒸発させ、放射性廃液を濃縮し、て、放
射性廃液を水蒸気と濃縮液とに分離する。また同膜蒸留
器（８）で分離した水蒸気を水蒸気管路Ｏりを経て凝縮
器（１０へ送り、ここで冷却水管路側を流れる冷却水に
よって冷却、凝縮し７、次いで凝縮水を脱塩塔ポンプ０
ωによって脱塩塔０７）へ送り、間膜塩［答面で浄化し
、た後、系外へ排出する。The radioactive waste liquid in the raw water tank (1) is sent to the tank (<V&m tank) (3) by the raw water pump (2), and then the radioactive waste liquid in the same tank (circulation tank) (3) is sent to the pump (
membrane distillation pump) (5) to the filter (6) where suspended solids in the radioactive waste are removed, and then the heater (
7), where it is heated to about 70 to 95°C and then sent to a membrane distiller (8), where the radioactive waste liquid is separated into water stem gas and condensed liquid. That is, water (1120
) is permeated and evaporated, the radioactive waste liquid is concentrated, and the radioactive waste liquid is separated into steam and concentrated liquid. In addition, the water vapor separated by the membrane distiller (8) is sent to the condenser (10) via the steam pipe O, where it is cooled and condensed by the cooling water flowing through the cooling water pipe. pump 0
It is sent to the desalination tower 07) by ω, and after being purified by the membrane salt [returning surface], it is discharged from the system.
一方、前記膜蒸留器（８）で分離した濃縮液を濃縮液管
路（９）→三方弁００）を経てタンク（循環タンク）（
３）内へ戻す。またタンク（ＶＩＪＩタンク）（３）内
の液位をレベル計（４）により検出し７、液位が低下す
れば、レベル計（４）の検出信号を原水ポンプ（２）へ
送って、同原水ポンプ（２）を再度起動し２、放射性廃
液を原水タンク（１）からタンク（循環タンク）（３）
内へ送って、タンク（Ｗｉｌｌタンク）（３）内の液位
を所定レベルに保持する。またタンク（′４環タンク）
（３）内の溶質濃度が所定値に達すると、原水ポンプ（
２）を停止、原水の供給を止めるとともに、三方弁ＱΦ
を切り換え、蒸留水を蒸留水循環管路（２１）を経て、
原水タンク（１）へ戻しながら、高濃縮運転を行なう。On the other hand, the concentrated liquid separated by the membrane distiller (8) is passed through the concentrated liquid pipe (9) → three-way valve 00) to a tank (circulation tank) (
3) Return inside. In addition, the liquid level in the tank (VIJI tank) (3) is detected by a level meter (4)7, and if the liquid level decreases, the detection signal of the level meter (4) is sent to the raw water pump (2), and the same Start the raw water pump (2) again 2, and transfer the radioactive waste liquid from the raw water tank (1) to the tank (circulation tank) (3)
The liquid level in the tank (Will tank) (3) is maintained at a predetermined level. Also tank ('4-ring tank)
When the solute concentration in (3) reaches a predetermined value, the raw water pump (
2), stop the supply of raw water, and close the three-way valve QΦ.
The distilled water is passed through the distilled water circulation pipe (21).
High concentration operation is performed while returning the raw water to the tank (1).
而してタンク（ｗｉ環タンク）（３）内の溶質濃度が目
標値に達すると、三方弁０ωを切り換え、ａ槽液を固化
装置θ０へ送り、ここで固化操作を行って、固化体０９
）を得る。When the solute concentration in the tank (wi ring tank) (3) reaches the target value, the three-way valve 0ω is switched and the liquid in tank a is sent to the solidification device θ0, where the solidification operation is performed to form a solidified body 09.
).
また膜蒸留器（８）の疏水性均質膜の透過性能が低下し
たときには、逆洗空気を逆洗空気管路θ■から水蒸気管
路０２）を経て膜蒸留器（８）の疏水性均質膜へ送り、
同疏水性均質膜に付着し７ている懸濁物質やクラッドを
逆洗空気によって除去し、て疏水性均質膜の逆洗を行っ
て）、疏水性均質膜の透過性能を保持する。In addition, when the permeation performance of the hydrophobic homogeneous membrane of the membrane distiller (8) decreases, the backwash air is passed from the backwash air pipe θ■ to the water vapor pipe 02) to the hydrophobic homogeneous membrane of the membrane distiller (8). send to
Suspended substances and crud attached to the hydrophobic homogeneous membrane are removed by backwashing air, and the hydrophobic homogeneous membrane is backwashed) to maintain the permeation performance of the hydrophobic homogeneous membrane.
なお前記三方弁ＱＯ及び蒸留水循環管路（２１）が前記
した蒸留水を上流側へ循環する循環手段を構成するもの
である。The three-way valve QO and the distilled water circulation pipe (21) constitute a circulation means for circulating the distilled water to the upstream side.
なお前記膜蒸留器（８）として疏水性多孔質膜を利用し
た膜蒸留器を使用した場合、処理液中にクラッド等の固
形分があると、膜の細孔を塞ぎ、膜の分離性能を阻害す
る。また多孔質膜では処理液中の溶存ガスが膜を透過し
、蒸留水側に移行する。Note that when a membrane distiller using a hydrophobic porous membrane is used as the membrane distiller (8), if solids such as crud are present in the treated liquid, the pores of the membrane will be blocked and the separation performance of the membrane will be affected. inhibit. Furthermore, in the case of a porous membrane, dissolved gas in the treatment liquid passes through the membrane and transfers to the distilled water side.
このため溶存ガス成分に放射性ガスが含有されている場
合には透過するガス分を常時排気する必要が生しる等の
問題点が生じる。For this reason, if the dissolved gas component contains radioactive gas, problems arise such as the need to constantly exhaust the permeating gas.
しかるに前記実施例においては、膜蒸留器（８）におけ
る疏水性多孔質膜に代えて疏水性均質膜を適用し、たこ
とによって、このような問題点を解決するものである。However, in the above embodiment, a hydrophobic homogeneous membrane is used in place of the hydrophobic porous membrane in the membrane distiller (8), thereby solving such problems.
（発明の効果）
本発明に係る放射性廃液処理装置によれば前記したよう
に、タンクとポンプと膜蒸留器との間に放射性廃液をＷ
ｉ環させてＰＡ縮槽液得る放射性廃液濃縮手段と、前記
膜蒸留器によって分離した水蒸気を凝縮器によって凝縮
させる蒸留水回収手段に加えて、前記濃縮液の濃度が一
定値を超えた時つ１、または蒸留水の水質が一定値に達
した時点以後、。(Effects of the Invention) According to the radioactive waste liquid treatment apparatus according to the present invention, as described above, the radioactive waste liquid is disposed between the tank, the pump, and the membrane distiller.
In addition to a radioactive waste liquid concentrating means for obtaining a PA condensation tank liquid by i-ring, and a distilled water recovery means for condensing the water vapor separated by the membrane distiller in a condenser, a radioactive waste liquid concentrating means is provided. 1, or after the quality of distilled water reaches a certain value.
得られた蒸留水を上流側へｌＦｔするＷｉ環手段を設４
Ｊたこ古によって、本発明の装置によって得られる透過
水の水質を、常時所定条件を満足し５うるものとし７、
また処理液を目標濃度まで高濃度し、うろものである。A Wi ring means is installed to transport the obtained distilled water to the upstream side.4
According to J. Takoko, the quality of the permeated water obtained by the device of the present invention should always satisfy predetermined conditions.
In addition, the treatment liquid is concentrated to a target concentration and is scaly.
請求項２の発明は、前記膜蒸留器を、疏水性均質膜を用
いた膜１留器より構成したことによって、処理液中に固
形分があっても膜の分離性能が悪影響を受けることがな
く、また疏水性均質膜は水蒸気以外のガス分を透過しな
いため、運転中に膜の２次側（透過側）の負圧を保持す
るための真空ポンプの稼動率の低減を図ることができる
。According to the second aspect of the invention, since the membrane distiller is constituted by a single membrane distiller using a hydrophobic homogeneous membrane, the separation performance of the membrane is not adversely affected even if there is solid content in the treated liquid. Furthermore, since hydrophobic homogeneous membranes do not allow gases other than water vapor to pass through, it is possible to reduce the operating rate of the vacuum pump that maintains negative pressure on the secondary side (permeation side) of the membrane during operation. .
第１図は本発明に係る放射性廃液処理装置の一実施例を
示す系統図である。
（１）・・・原水タンク、 （２）・・・原水ポン
プ、（３）・・・タンク、（４）・・・レベル計、（５
）・・・循環ポンプ、 （６）・・・フィルタ、（
７）・・・フィルタ、 （８）・・・膜蒸留器、
（９）・・・ａｈｉｉ液管路、 ００）・・・三方
弁、（１１）・・・凝縮器、 θり・・・水蒸
気管路、０３１・・・逆洗空気管路、 圓・・・冷却
水管路、θつ・・・真空ポンプ、 ０ω・・・脱塩
塔ポンプ、０力・・・脱塩塔、 ０８）・・・
固化装置、θワ）・・・固化体、 ＱＯ・・・
三方弁、（２１）・・・蒸留水ｗｉ環管路。FIG. 1 is a system diagram showing an embodiment of a radioactive waste liquid treatment apparatus according to the present invention. (1)... Raw water tank, (2)... Raw water pump, (3)... Tank, (4)... Level meter, (5
)...Circulation pump, (6)...Filter, (
7)...filter, (8)...membrane distiller,
(9)...ahii liquid pipe line, 00)...three-way valve, (11)...condenser, θri...steam pipe line, 031...backwash air pipe line, round...・Cooling water pipe, θ...vacuum pump, 0ω...desalination tower pump, 0 force...desalination tower, 08)...
Solidification device, θwa)...solidified body, QO...
Three-way valve, (21)... Distilled water wi ring pipe.
Claims (1)
循環させて濃縮液を得る放射性廃液濃縮手段と、前記膜
蒸留器により分離した水蒸気を凝縮器によって凝縮させ
る蒸留水回収手段とを具えた膜蒸留式の放射性廃液処理
装置において、前記濃縮液の濃度が一定値を超えた時点
、または蒸留水の水質が一定値に達した時点以後、得ら
れた蒸留水を上流側へ循環する循環手段を具備してなる
ことを特徴とする放射性廃液処理装置。 ２、前記膜蒸留器は疏水性均質膜を用いた膜蒸留器より
構成された請求項１記載の放射性廃液処理装置。[Claims] 1. Radioactive waste liquid concentrating means for obtaining a concentrated liquid by circulating radioactive waste liquid between a tank, a pump, and a membrane distiller, and a distillation method for condensing water vapor separated by the membrane distiller using a condenser. In a membrane distillation type radioactive waste liquid treatment equipment equipped with a water recovery means, after the concentration of the concentrated liquid exceeds a certain value or the quality of the distilled water reaches a certain value, the obtained distilled water is A radioactive waste liquid treatment device characterized by comprising a circulation means for circulating to an upstream side. 2. The radioactive waste liquid treatment apparatus according to claim 1, wherein the membrane distiller is a membrane distiller using a hydrophobic homogeneous membrane.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14668789A JPH0313896A (en) | 1989-06-12 | 1989-06-12 | Radioactive waste liquid disposal facility |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14668789A JPH0313896A (en) | 1989-06-12 | 1989-06-12 | Radioactive waste liquid disposal facility |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0313896A true JPH0313896A (en) | 1991-01-22 |
Family
ID=15413308
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP14668789A Pending JPH0313896A (en) | 1989-06-12 | 1989-06-12 | Radioactive waste liquid disposal facility |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0313896A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2018516751A (en) * | 2015-06-08 | 2018-06-28 | ローベルト ボッシュ ゲゼルシャフト ミット ベシュレンクテル ハフツング | Device for providing sterile water for injection |
-
1989
- 1989-06-12 JP JP14668789A patent/JPH0313896A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2018516751A (en) * | 2015-06-08 | 2018-06-28 | ローベルト ボッシュ ゲゼルシャフト ミット ベシュレンクテル ハフツング | Device for providing sterile water for injection |
| US11358100B2 (en) | 2015-06-08 | 2022-06-14 | Pharmatec GmbH | Arrangement for providing sterile water for injection purposes |
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