JPH0719032Y2 - Radioactive waste liquid treatment device - Google Patents
Radioactive waste liquid treatment deviceInfo
- Publication number
- JPH0719032Y2 JPH0719032Y2 JP1462988U JP1462988U JPH0719032Y2 JP H0719032 Y2 JPH0719032 Y2 JP H0719032Y2 JP 1462988 U JP1462988 U JP 1462988U JP 1462988 U JP1462988 U JP 1462988U JP H0719032 Y2 JPH0719032 Y2 JP H0719032Y2
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- JP
- Japan
- Prior art keywords
- waste liquid
- radioactive waste
- radioactive
- liquid
- tank
- 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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- Separation Using Semi-Permeable Membranes (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Description
【考案の詳細な説明】 （産業上の利用分野） 本考案は，原子力発電所等に適用される放射性廃液処理
装置に関するものである。DETAILED DESCRIPTION OF THE INVENTION (Industrial field of application) The present invention relates to a radioactive liquid waste treatment apparatus applied to a nuclear power plant or the like.
（従来の技術） 従来は，原子力発電所から発生する放射性廃液を蒸発器
により濃縮処理し、蒸留液を脱塩塔へ導いて，浄化した
後，系外へ放出する一方，濃縮液をセメント固化，アス
フアルト固化，ポリマー固化等により処理している。な
お放射性廃液の組成の代表的な一例としては， ホウ酸（H3BO3）等＋放射性物質（58Co，60Co，54H
n，59Fe等）があり， 他の例としては， ボウ硝（Na2SO4）等＋放射性物質（58Co，60Co，54
Hn，59Fe等）がある。(Prior Art) Conventionally, radioactive waste liquid generated from a nuclear power plant is concentrated by an evaporator, the distillate is guided to a desalting tower, purified, and then discharged outside the system, while the concentrate is solidified by cement. , Asphalt solidification, polymer solidification, etc. A typical example of the composition of radioactive waste liquid is boric acid (H 3 BO 3 ) + radioactive material ( 58 Co, 60 Co, 54 H
n, 59 Fe, etc.), and other examples include glauber's salt (Na 2 SO 4 ) + radioactive materials ( 58 Co, 60 Co, 54
Hn, 59 Fe, etc.).
（考案が解決しようとする課題） 前記従来の放射性廃液処理装置では，（Ｉ）原子力発電
所から発生する放射性廃液を蒸発器により濃縮処理して
いるが，この場合には，放射性廃液の蒸発に伴う放射性
物質のキヤリオーバがあり，このため，大型の蒸留塔が
必要で，蒸留塔の蒸発器に占めるコストの割合が大きく
て，設備費が嵩む。（II）また放射性廃液の蒸発温度が
110℃程度の高温のため，伝熱管等が腐食し易くて，伝
熱管等に耐腐食性の高級材料を使用する必要があり，こ
の点からも設備費が嵩む。また放射性廃液の蒸発温度が
110℃程度と高温のために，腐食性物質（ハロゲン化合
物等）の濃縮制限を余儀なくされている。(Problems to be Solved by the Invention) In the conventional radioactive liquid waste treatment apparatus, (I) the radioactive liquid waste generated from a nuclear power plant is concentrated by an evaporator. In this case, the radioactive liquid waste is evaporated. There is a carry-over of radioactive materials, which requires a large-scale distillation column, which makes up a large proportion of the cost in the evaporator of the distillation column, which increases equipment costs. (II) Also, the evaporation temperature of radioactive waste liquid
Due to the high temperature of around 110 ℃, the heat transfer tubes are easily corroded, and it is necessary to use high-grade corrosion-resistant materials for the heat transfer tubes, which also increases the equipment cost. Also, the evaporation temperature of radioactive waste liquid
Due to the high temperature of around 110 ℃, it is unavoidable to limit the concentration of corrosive substances (halogen compounds, etc.).
本考案は前記の問題点に鑑み提案するものであり，その
目的とする処は，大型の蒸留塔が不要な上に，伝熱管等
に耐腐食性の高級材料を使用する必要がなくて，設備費
を低減できる。腐食性物質の濃縮制限を無くすことがで
きる。さらに凝縮水の水質を格段に向上できる放射性廃
液処理装置を提供しようとする点にある。The present invention is proposed in view of the above problems, and its purpose is to eliminate the need for a large-scale distillation column and to use high-grade corrosion-resistant materials for heat transfer tubes, Equipment costs can be reduced. It is possible to eliminate the restriction on the concentration of corrosive substances. Another object is to provide a radioactive liquid waste treatment device capable of significantly improving the quality of condensed water.
（課題を解決するための手段） 上記目的を達成するために，本考案の放射性廃液処理装
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濃縮手段と，上記膜
蒸留器により分離した水蒸気を凝縮器により凝縮させた
のち脱塩塔により浄化する凝縮水浄化手段と，上記放射
性廃液濃縮手段により濃縮した濃縮液を固化装置により
固化する濃縮液固化手段とを具えている。(Means for Solving the Problems) In order to achieve the above object, the radioactive waste liquid treatment apparatus of the present invention is a radioactive waste liquid concentrator for obtaining a concentrated liquid by circulating the radioactive waste liquid between a tank, a pump and a membrane distiller. Means, condensed water purification means for condensing the water vapor separated by the membrane distiller by a condenser and then purifying by a desalting tower, and concentrated liquid solidification for solidifying the concentrated liquid concentrated by the radioactive waste liquid concentrating means by a solidifying device And means.
（作用） 本考案の放射性廃液処理装置は前記のように構成されて
おり，放射性廃液を放射性廃液濃縮手段，即ち，タンク
とポンプと膜蒸留器との間に循環させて，放射性廃液を
濃縮し，上記膜蒸留器により分離した水蒸気を凝縮器に
より凝縮させたのち，脱塩塔により浄化して，系外へ排
出し，上記放射性廃液濃縮手段により濃縮した濃縮液を
固化装置により固化して，固化体を得る。(Operation) The radioactive liquid waste treatment apparatus of the present invention is constructed as described above, and the radioactive liquid waste is concentrated by circulating the radioactive liquid waste between the radioactive liquid waste concentrating means, that is, the tank, the pump and the membrane distiller. After the water vapor separated by the membrane distiller is condensed by the condenser, it is purified by the desalting tower, discharged to the outside of the system, and the concentrated liquid concentrated by the radioactive waste liquid concentrating means is solidified by the solidifying device, Obtain a solidified body.
（実施例） 次に本考案の放射性廃液処理装置を第1,2図に示す一実
施例により説明すると，第１図の（１）が原水タンク，
（２）が原水ポンプ，（３）がタンク（循環タンク），
（４）がレベル計，（５）がポンプ（膜蒸留ポンプ），
（17）がフイルタ，（18）がヒータ，（６）が膜蒸留
器，（16）が濃縮液管路，（12）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（膜蒸留
ポンプ）（５）→フイルタ（17）→ヒータ（18）→膜蒸
留器（６）→濃縮液管路（16）→三方弁（12）→タンク
（循環タンク）（３）に循環するようになっている。ま
た上記膜蒸留器（６）は，第２図に示すように疏水性多
孔質膜（ポリテトラフルオルエチレン，ポリプロピレ
ン，ポリエチレン等の疏水性多孔質膜）（6a）と同疏水
性多孔質膜（6a）に対しギヤツプを介して対向設置した
冷却面（6b）とを有し，疏水性多孔質膜（6a）の片側に
供給した放射性廃液（例えばホウ酸（H3BO3）＋放射性
物質）から水（H2O）のみを透過，蒸発させて，放射性
廃液を濃縮するようになっている。このとき，疏水性多
孔質膜（6a）の冷却面（6b）側（二次側）で水の透過，
蒸発を促進するために，同二次側を負圧（約100mmHg以
下）に保持する。同第２図の（Ａ）は冷却面（6a）に付
着した凝縮水である。また第１図の（７）が凝縮器，
（15）が上記膜蒸留器（６）と同濃縮器（７）とを連結
する水蒸気管路，（19）が同水蒸気管路（15）に接続し
た逆洗空気管路，（11）が同濃縮器（７）に設けた冷却
水管路，（８）が同濃縮器（７）の側部に接続した真空
ポンプ，（９）が同濃縮器（７）の底部に接続した脱塩
塔ポンプ，（10）が同脱塩塔ポンプ（９）に接続した脱
塩塔（膜蒸留器（６）のバツクアツプ機器），（13）が
上記三方弁（12）に接続した固化装置，（14）が固化体
である。(Embodiment) Next, the radioactive liquid waste treatment apparatus of the present invention will be described with reference to an embodiment shown in FIGS. 1 and 2. (1) of FIG.
(2) is a raw water pump, (3) is a tank (circulation tank),
(4) is a level meter, (5) is a pump (membrane distillation pump),
(17) is a filter, (18) is a heater, (6) is a membrane distiller, (16) is a concentrate line, (12) is a three-way valve, and the radioactive waste liquid in the raw water tank (1) is pumped to the raw water ( The radioactive waste liquid in the tank (circulation tank) (3) is pumped (membrane distillation pump) (5) → filter (17) → heater (18) so as to be supplied to the tank (circulation tank) (3) via 2). ) → Membrane distiller (6) → concentrated liquid pipe line (16) → three-way valve (12) → tank (circulation tank) (3). The membrane distiller (6) has a hydrophobic porous membrane (6a) and a hydrophobic porous membrane (hydrophobic porous membrane of polytetrafluoroethylene, polypropylene, polyethylene, etc.) (6a) as shown in FIG. Radioactive waste liquid (eg boric acid (H 3 BO 3 ) + radioactive substance) that has a cooling surface (6b) installed opposite to (6a) via a gear cup and is supplied to one side of the hydrophobic porous membrane (6a) ), Only water (H 2 O) permeates and evaporates to concentrate the radioactive liquid waste. At this time, water permeates on the cooling surface (6b) side (secondary side) of the hydrophobic porous membrane (6a),
The secondary side is maintained at a negative pressure (about 100 mmHg or less) to promote evaporation. FIG. 2A shows condensed water attached to the cooling surface (6a). Further, (7) in FIG. 1 is a condenser,
(15) is a steam line connecting the membrane distiller (6) and the condenser (7), (19) is a backwash air line connected to the steam line (15), and (11) is A cooling water pipe provided in the concentrator (7), a vacuum pump in which (8) is connected to the side of the concentrator (7), and a desalting tower in which (9) is connected to the bottom of the concentrator (7). Pump, (10) desalting tower (back-up device of membrane distiller (6)) connected to the same desalting tower pump (9), (13) solidification device connected to the three-way valve (12), (14 ) Is a solidified body.
次に前記第1,2図に示す放射性廃液処理装置の作用を具
体的に説明する。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（循環タンク）（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）によりフルイタ
（17）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（18）へ送り，ここで70〜95℃程度に
加熱し，次いで膜蒸留器（６）へ送り，ここで放射性廃
液を水蒸気と凝縮液とに分離する。即ち，疏水性多孔質
膜（6a）の片側に供給した放射性廃液（例えばホウ酸
（H3BO3）＋放射性物質）から水（H2O）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
凝縮液とに分離する。また同膜蒸留器（６）で分離した
水蒸気を水蒸気管路（15）を経て凝縮器（７）へ送り，
ここで冷却水管路（11）を流れる冷却水により冷却，凝
縮し，次いで凝縮水を脱塩塔ポンプ（９）により脱塩塔
（10）へ送り，ここで浄化した後，系外へ排出する。一
方，上記膜蒸留器（６）で分離した濃縮液を濃縮液管路
（16）→三方弁（12）を経てタンク（循環タンク）
（３）内へ戻す。またタンク（循環タンク）（３）内の
液位をレベル計（４）により検出し，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，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（循環タンク）（３）内の液位を所定レ
ベルに保持する。またタンク（循環タンク）（３）内の
溶質濃度が所定値に達すると，三方弁（12）を切り換
え，濃縮液を固化装置（13）へ送り，ここで固化操作を
行って，固化体（14）を得る。また膜蒸留器（６）の疏
水性多孔質膜（6a）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（19）から水蒸気管路（15）を経
て膜蒸留器（６）の疏水性多孔質膜（6a）へ送り，同疏
水性多孔質膜（6a）に付着している懸濁物質やクラツド
を逆洗空気により除去して（疏水性多孔質膜（6a）の逆
洗を行って），疏水性多孔質膜（6a）の透過性を保持す
る。Next, the operation of the radioactive liquid waste treatment apparatus shown in FIGS. 1 and 2 will be specifically described. The radioactive waste liquid in the raw water tank (1) is sent to the tank (circulation tank) (3) by the raw water pump (2), and then the radioactive waste liquid in the same tank (circulation tank) (3) is pumped (membrane distillation pump) ( 5) Send it to the filter (17) where it removes suspended solids in the radioactive waste liquid, then sends it to the heater (18) where it is heated to about 70-95 ° C and then to the membrane distiller (6) It is sent to separate the radioactive waste liquid into steam and condensate. That is, only the water (H 2 O) permeates and evaporates from the radioactive waste liquid (eg boric acid (H 3 BO 3 ) + radioactive substance) supplied to one side of the hydrophobic porous membrane (6a) to concentrate the radioactive waste liquid. The radioactive waste liquid is separated into steam and condensate. In addition, the steam separated in the membrane distillation device (6) is sent to the condenser (7) via the steam pipe line (15),
Here, it is cooled and condensed by the cooling water flowing through the cooling water pipe (11), and then the condensed water is sent to the desalting tower (10) by the desalting tower pump (9), where it is purified and then discharged to the outside of the system. . On the other hand, the concentrated liquid separated by the membrane distiller (6) is passed through the concentrated liquid pipe (16) → the three-way valve (12) to a tank (circulation tank).
(3) Return to inside. In addition, the liquid level in the tank (circulation tank) (3) is detected by the level meter (4), and if the liquid level drops, the detection signal of the level meter (4) is sent to the raw water pump (2), The pump (2) is started again, and the radioactive liquid waste is sent from the raw water tank (1) into the tank (circulation tank) (3) to maintain the liquid level in the tank (circulation tank) (3) at a predetermined level. When the solute concentration in the tank (circulation tank) (3) reaches a predetermined value, the three-way valve (12) is switched and the concentrated liquid is sent to the solidification device (13), where the solidification operation is performed and the solidified body ( 14) get. Further, when the permeation performance of the hydrophobic porous membrane (6a) of the membrane distiller (6) is lowered, the backwash air is passed from the backwash air pipe line (19) through the steam pipe line (15) to the membrane distiller (6). ) Is sent to the hydrophobic porous membrane (6a), and the suspended substances and the clod adhering to the hydrophobic porous membrane (6a) are removed by backwashing air (the hydrophobic porous membrane (6a) By carrying out backwashing), the permeability of the hydrophobic porous membrane (6a) is maintained.
第３図は，前記フルイタ（17）を省略し，ヒータ（18）
と膜蒸留器（６）とを接続する管路に三方弁（20）を介
して逆洗空気管路（19）を取付けた以外，前記第1,2図
に示した放射性廃液処理装置と同様に構成した他の実施
例で，この実施例でも，前記と同様の作用が行われる。
なおフルイタ（17）があると，同フルイタ（17）に二次
廃棄物が溜まって，フルイタ（17）を交換する際，被曝
の可能性があるが，本実施例では，フルイタ（17）が無
くて，被曝の惧れがない。FIG. 3 shows the heater (18) with the fluter (17) omitted.
Same as the radioactive waste liquid treatment apparatus shown in FIGS. 1 and 2 except that the backwash air pipe line (19) is attached to the pipe line connecting the membrane distiller (6) with the three-way valve (20). In the other embodiment configured as described above, also in this embodiment, the same operation as described above is performed.
If there is a fluita (17), secondary waste will accumulate in the fluita (17) and there is a possibility of exposure when replacing the fluita (17), but in this embodiment, the fluita (17) There is no fear of radiation exposure.
（考案の効果） 本考案の放射性廃液処理装置は前記のように放射性廃液
を放射性廃液濃縮手段，即ち，タンクとポンプと膜蒸留
器との間に循環させて，放射性廃液を濃縮し，上記膜蒸
留器により分離した水蒸気を凝縮器により凝縮させたの
ち，脱塩塔により浄化して，系外へ排出し，上記放射性
廃液濃縮手段により濃縮した濃縮液を固化装置により固
化して，固化体を得るようにしており，上記膜蒸留器で
の蒸発が膜を介したマイルドな蒸発になり，放射性廃液
の蒸発に伴って生じていた放射性物質のキヤリオーバを
なくすことができて，蒸留塔を不要にできる。また放射
性廃液濃縮手段を循環する放射性廃液の温度が70〜95℃
程度でよく，前記従来のように放射性廃液の蒸発温度が
110℃程度と高温な場合に比べると，低温処理になっ
て，伝熱管等に耐腐食性の高級材料を使用する必要がな
く，上記のように蒸留塔を不要にできる点と相俟って設
備費を低減できる。(Effect of the Invention) As described above, the radioactive waste liquid treatment apparatus of the present invention concentrates the radioactive waste liquid by circulating the radioactive waste liquid between the radioactive waste liquid concentrating means, that is, the tank, the pump and the membrane distiller. After the water vapor separated by the distiller is condensed by the condenser, it is purified by the desalting tower, discharged to the outside of the system, and the concentrated liquid concentrated by the radioactive waste liquid concentrating means is solidified by the solidifying device to form a solidified body. The evaporation in the above-mentioned membrane distiller becomes mild evaporation through the membrane, and it is possible to eliminate the carry-over of radioactive materials that was generated with the evaporation of radioactive waste liquid, thus eliminating the need for a distillation column. it can. The temperature of the radioactive waste liquid circulating in the radioactive waste liquid concentrating means is 70 to 95 ° C.
However, the evaporation temperature of the radioactive liquid waste is the same as the conventional one.
Compared with the case of a high temperature of about 110 ° C, it is a low-temperature treatment, and it is not necessary to use high-grade corrosion-resistant materials for heat transfer tubes, etc. Equipment costs can be reduced.
また上記のように低温処理になるので，腐食性物質（ハ
ロゲン化合物等）の濃縮制限を無くすことができる。Further, since the low temperature treatment is performed as described above, it is possible to eliminate the limitation of concentration of corrosive substances (halogen compounds, etc.).
また膜蒸留器により分離した水蒸気を凝縮器により凝縮
させたのち，脱塩塔により浄化して，系外へ排出するの
で，凝縮水の水質を前記従来の場合に比べると,10倍程
度と格段に向上できる効果がある。In addition, the water vapor separated by the membrane distiller is condensed by the condenser, then purified by the desalting tower and discharged to the outside of the system. Therefore, the quality of the condensed water is about 10 times that of the conventional case. There is an effect that can improve.
第１図は本考案に係わる放射性廃液処理装置の一実施例
を示す系統図，第２図は膜蒸留器の作用説明図，第３図
は同放射性廃液処理装置の他の実施例を示す系統図であ
る。 （３）……タンク，（５）……ポンプ，（６）……膜蒸
留器，（７）……凝縮器，（10）……脱塩塔，（13）…
…固化装置，（14）……固化体。FIG. 1 is a system diagram showing an embodiment of a radioactive liquid waste treatment apparatus according to the present invention, FIG. 2 is an explanatory view of the operation of a membrane distiller, and FIG. 3 is a system showing another embodiment of the radioactive liquid waste treatment apparatus. It is a figure. (3) ... tank, (5) ... pump, (6) ... membrane distiller, (7) ... condenser, (10) ... desalting tower, (13) ...
… Solidifying device, (14) …… Solidified body.
Claims (1)
廃液を循環させて濃縮液を得る放射性廃液濃縮手段と，
上記膜蒸留器により分離した水蒸気を凝縮器により凝縮
させたのち脱塩塔により浄化する凝縮水浄化手段と，上
記放射性廃液濃縮手段により濃縮した濃縮液を固化装置
により固化する濃縮液固化手段とを具えていることを特
徴とした放射性廃液処理装置。1. A radioactive waste liquid concentrating means for circulating a radioactive waste liquid between a tank, a pump and a membrane distiller to obtain a concentrated liquid,
Condensed water purification means for purifying the dewatering tower after condensing the water vapor separated by the membrane distiller by a condenser, and concentrated liquid solidification means for solidifying the concentrated liquid concentrated by the radioactive waste liquid concentrating means by a solidifying device. A radioactive waste liquid treatment device characterized by being provided.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1462988U JPH0719032Y2 (en) | 1988-02-08 | 1988-02-08 | Radioactive waste liquid treatment device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1462988U JPH0719032Y2 (en) | 1988-02-08 | 1988-02-08 | Radioactive waste liquid treatment device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01120697U JPH01120697U (en) | 1989-08-16 |
| JPH0719032Y2 true JPH0719032Y2 (en) | 1995-05-01 |
Family
ID=31226001
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1462988U Expired - Lifetime JPH0719032Y2 (en) | 1988-02-08 | 1988-02-08 | Radioactive waste liquid treatment device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0719032Y2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0961590A (en) * | 1995-08-25 | 1997-03-07 | Toshiba Corp | Radioactive waste liquid treating system |
-
1988
- 1988-02-08 JP JP1462988U patent/JPH0719032Y2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH01120697U (en) | 1989-08-16 |
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