JPH09189798A - Radioactive waste liquid treatment device - Google Patents

Radioactive waste liquid treatment device

Info

Publication number
JPH09189798A
JPH09189798A JP274796A JP274796A JPH09189798A JP H09189798 A JPH09189798 A JP H09189798A JP 274796 A JP274796 A JP 274796A JP 274796 A JP274796 A JP 274796A JP H09189798 A JPH09189798 A JP H09189798A
Authority
JP
Japan
Prior art keywords
waste liquid
concentrated
chlorine
tank
concentrated waste
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
Application number
JP274796A
Other languages
Japanese (ja)
Inventor
Shigeru Ozaki
繁 尾崎
Masami Yamazaki
正巳 山崎
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Engineering Corp
Toshiba Corp
Original Assignee
Toshiba Engineering Corp
Toshiba Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Toshiba Engineering Corp, Toshiba Corp filed Critical Toshiba Engineering Corp
Priority to JP274796A priority Critical patent/JPH09189798A/en
Publication of JPH09189798A publication Critical patent/JPH09189798A/en
Pending legal-status Critical Current

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Abstract

PROBLEM TO BE SOLVED: To make it possible to reconcentrate a waste liquid with a concentrator by dechlorinating the concentrated waste liquid produced in a nuclear power plant to reduce the yield of the concentrated waste liquid and operate treatment facilities efficiently. SOLUTION: A waste liquid tank 1 is connected to a concentrator 3, which is connected to a concentrated waste liquid tank 6. It is connected to a dechlorinating device 10, whose downstream side is connected to the upstream side of the concentrator 3. The waste liquid collected in the waste liquid collecting tank 1 is transferred by way of a waste liquid transfer line 2 to the concentrator 3 to be concentrated. If the concentration of the solid content or sodium sulfate in the concentrated waste liquid which is concentrated in the concentrator 3 and is discharged to the concentrated waste liquid tank 6 does not reach a prescribed value, the concentrated waste liquid in the concentrated waste liquid tank 6 is transferred to the dechlorinating device 10 to remove chlorine. The dechlorinated concentrated waste liquid is transferred from a concentrated waste liquid return line 11 through the waste liquid line 2 to the concentrator 3, where it is reconcentrated. If the concentration of the solid content or sodium sulfate reaches the prescribed value, the waste liquid is transferred to the concentrated waste liquid tank 6 and is treated in a solidifying device 8 to be solidified.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【発明の属する技術分野】本発明は原子力発電所などで
発生する放射性廃液中の塩素を除去し、効率的に廃液を
処理するための放射性廃液処理装置に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a radioactive liquid waste treatment apparatus for removing chlorine in a radioactive liquid waste generated in a nuclear power plant or the like and efficiently treating the liquid waste.

【0002】[0002]

【従来の技術】原子力発電所には放射性廃棄物処理設備
が設置されており、この設備によって発電所内で発生す
る放射性廃液をその性状に応じて、適切に処理し、廃棄
物の低減を図っている。
2. Description of the Related Art A nuclear power plant is equipped with a radioactive waste treatment facility. With this facility, radioactive waste liquid generated in the power plant is appropriately treated according to its properties to reduce waste. There is.

【0003】図4により従来の放射性廃液処理装置の一
例を説明する。図4において原子力発電所内で発生する
放射性廃液は廃液収集タンク1に収集され、収集した廃
液は廃液移送ライン2を流れて濃縮装置3へ供給され
る。廃液は濃縮装置3で濃縮蒸留され、蒸留水4は脱塩
処理後発電所内で再使用されるか、または放射能濃度が
十分に低いことを確認した後、原子力発電所外の海洋へ
放出される。
An example of a conventional radioactive liquid waste treatment apparatus will be described with reference to FIG. In FIG. 4, the radioactive liquid waste generated in the nuclear power plant is collected in the liquid waste collection tank 1, and the collected liquid waste flows through the liquid waste transfer line 2 and is supplied to the concentrator 3. The waste liquid is concentrated and distilled in the concentrator 3, and the distilled water 4 is reused in the power plant after desalting, or after confirming that the radioactivity concentration is sufficiently low, it is released to the ocean outside the nuclear power plant. It

【0004】一方、濃縮された濃縮廃液は濃縮装置3の
健全性を確保するため、濃縮装置3内での固形分濃度,
塩素濃度、または硫酸ナトリウム濃度が所定値に達した
場合、濃縮廃液排出ライン5を通して濃縮廃液タンク6
に排出され、一定期間貯蔵後に濃縮廃液移送ライン7か
ら固化装置8へ移送しセメントやプラスチックの固化材
と混合してドラム缶内に固化処理される。濃縮装置3内
での濃縮廃液排出の所定値の例を以下に示す。
On the other hand, in order to ensure the soundness of the concentrating device 3, the concentrated concentrated waste liquid has a solid content concentration in the concentrating device 3,
When the chlorine concentration or the sodium sulfate concentration reaches a predetermined value, the concentrated waste liquid tank 6 is passed through the concentrated waste liquid discharge line 5.
After being stored for a certain period of time, the concentrated waste liquid is transferred from the concentrated waste liquid transfer line 7 to a solidifying device 8 where it is mixed with a solidifying material such as cement or plastic and solidified in a drum can. An example of a predetermined value for discharging the concentrated waste liquid in the concentrating device 3 is shown below.

【0005】[0005]

【表1】 [Table 1]

【0006】[0006]

【発明が解決しようとする課題】ところで、従来の放射
性廃液処理装置においては、濃縮装置3で濃縮された濃
縮廃液はその濃度が所定値に達した場合、濃縮廃液タン
ク6に排出されるが、その所定値と云うものほとんどが
塩素濃度の数値によるものである。したがって、濃縮廃
液タンク6内の廃液は固形分濃度や硫酸ナトリウム濃度
が実際の所定値よりも低い状態となっている。このた
め、濃縮廃液タンク6内に貯蔵する濃縮廃液の貯蔵効率
が低く、固化装置8の運転頻度が増加するという課題が
ある。
In the conventional radioactive liquid waste treatment device, the concentrated liquid waste concentrated in the concentrating device 3 is discharged to the concentrated liquid waste tank 6 when its concentration reaches a predetermined value. Most of the predetermined values are based on the numerical value of chlorine concentration. Therefore, the waste liquid in the concentrated waste liquid tank 6 is in a state where the solid content concentration and the sodium sulfate concentration are lower than the actual predetermined values. Therefore, there is a problem that the storage efficiency of the concentrated waste liquid stored in the concentrated waste liquid tank 6 is low and the operating frequency of the solidification device 8 increases.

【0007】また、濃縮廃棄タンク6の貯蔵量が所定量
となると、濃縮廃液移送ライン7から固化装置8に移送
してセメントやプラスチックの固化材と混合してドラム
缶内に固化されるが、濃縮廃液の固形分濃度や硫酸ナト
リウム濃度が淡いため、減容が十分でなく、ドラム缶の
発生本数が増加する課題がある。
When the storage amount in the concentrated waste tank 6 reaches a predetermined amount, the concentrated waste liquid is transferred from the concentrated waste liquid transfer line 7 to the solidification device 8 and mixed with the cement or plastic solidifying material to be solidified in the drum can. Since the solid content concentration and the sodium sulfate concentration of the waste liquid are light, there is a problem that the volume reduction is not sufficient and the number of drums generated increases.

【0008】本発明は上記課題を解決するためになされ
たもので、その目的は原子力発電所などで発生する放射
性廃液中の塩素を除去し、再度濃縮可能な廃液とするこ
とにより、効率的に廃液の処理,貯蔵ができる放射性廃
液処理装置を提供することにある。
The present invention has been made to solve the above problems, and its purpose is to efficiently remove chlorine in radioactive waste liquid generated in a nuclear power plant or the like to make a waste liquid that can be concentrated again. An object of the present invention is to provide a radioactive liquid waste treatment device capable of treating and storing liquid waste.

【0009】[0009]

【課題を解決するための手段】本発明は原子力発電所で
発生する放射性廃液を収集する廃液収集タンクと、この
収集タンク内の廃液を濃縮する濃縮装置と、この濃縮廃
液を貯蔵する濃縮廃液タンクとこの濃縮廃液タンク内の
濃縮廃液中の塩素を除去する塩素除去装置と、塩素除去
後の濃縮廃液を前記濃縮装置へ戻す濃縮廃液戻しライン
とを具備したことを特徴とする。
The present invention relates to a waste liquid collection tank for collecting radioactive waste liquid generated in a nuclear power plant, a concentrating device for concentrating the waste liquid in the collection tank, and a concentrated waste liquid tank for storing the concentrated waste liquid. And a chlorine removing device for removing chlorine in the concentrated waste liquid in the concentrated waste liquid tank, and a concentrated waste liquid returning line for returning the concentrated waste liquid after chlorine removal to the concentrating device.

【0010】また、本発明は原子力発電所で発生する放
射性廃液を収集する廃液収集タンクと、この収集タンク
内の廃液を濃縮する濃縮装置と、前記廃液収集タンク内
の廃液を濃縮する前にこの廃液中の塩素を除去する塩素
除去装置と、塩素除去後の廃液を廃液収集タンクへ戻す
戻しラインとを具備したことを特徴とする。
The present invention also relates to a waste liquid collecting tank for collecting radioactive waste liquid generated in a nuclear power plant, a concentrating device for concentrating the waste liquid in the collecting tank, and a concentrating device for concentrating the waste liquid in the waste liquid collecting tank. It is characterized by comprising a chlorine removing device for removing chlorine in the waste liquid, and a return line for returning the waste liquid after the chlorine removal to the waste liquid collecting tank.

【0011】さらに、本発明は原子力発電所で発生する
放射性廃液を収集する廃液収集タンクと、この収集タン
ク内の廃液を濃縮する濃縮装置と、この濃縮装置内の濃
縮廃液中の塩素を除去する塩素除去装置と、塩素除去後
の濃縮廃液を前記濃縮装置へ戻す濃縮廃液戻しラインと
を具備したことを特徴とする。
Further, according to the present invention, a waste liquid collecting tank for collecting radioactive waste liquid generated in a nuclear power plant, a concentrating device for concentrating the waste liquid in the collecting tank, and chlorine in the concentrated waste liquid in the concentrating device are removed. It is characterized by comprising a chlorine removing device and a concentrated waste liquid returning line for returning the concentrated waste liquid after chlorine removal to the concentrating device.

【0012】本発明装置によれば、濃縮装置で濃縮した
廃液中の塩素成分を除去することにより、再度濃縮処理
が可能となる。また、廃液収集タンクで収集した廃液中
の塩素成分を除去することにより、濃縮装置での濃縮度
を上げることが可能となる。そのため、廃棄物として発
生する濃縮廃液の発生量を低減することができ、設備の
効率的な運用が可能となる。
According to the apparatus of the present invention, the chlorine component in the waste liquid concentrated by the concentrating device is removed so that the concentration process can be performed again. Further, by removing the chlorine component in the waste liquid collected in the waste liquid collection tank, it becomes possible to increase the degree of concentration in the concentrator. Therefore, the amount of concentrated waste liquid generated as waste can be reduced, and the equipment can be operated efficiently.

【0013】[0013]

【発明の実施の形態】図1により本発明に係る放射性廃
液処理装置の第1の実施の形態について説明する。な
お、図1中、図4と同一部分には同一符号を付してい
る。図1において廃液収集タンク1は廃液移送ライン2
を介して濃縮装置3に接続している。濃縮装置3は濃縮
廃液排出ライン5を介して濃縮廃液タンク6に接続し、
濃縮廃液移送ライン7を介して固化装置8に接続してい
る。
BEST MODE FOR CARRYING OUT THE INVENTION A first embodiment of a radioactive liquid waste treatment apparatus according to the present invention will be described with reference to FIG. In FIG. 1, the same parts as those in FIG. 4 are denoted by the same reference numerals. In FIG. 1, the waste liquid collection tank 1 is a waste liquid transfer line 2
It is connected to the concentrating device 3 via. The concentrating device 3 is connected to a concentrated waste liquid tank 6 via a concentrated waste liquid discharge line 5,
It is connected to the solidification device 8 via the concentrated waste liquid transfer line 7.

【0014】一方、濃縮廃液移送ライン7から分岐して
濃縮廃液分岐ライン9が接続し、この濃縮廃液分岐ライ
ン9は塩素除去装置10に接続している。この塩素除去装
置10には濃縮廃液戻しライン11が接続し、廃液収集タン
ク1と濃縮装置3を接続する廃液移送ライン2に接続し
ている。塩素除去装置10は例えば電気分解法や電気透析
法,吸着法などの方法によって塩素を除去するものであ
る。
On the other hand, a concentrated waste liquid transfer line 7 is branched and connected to a concentrated waste liquid branch line 9, which is connected to a chlorine removing device 10. A concentrated waste liquid return line 11 is connected to the chlorine removal device 10, and is connected to a waste liquid transfer line 2 that connects the waste liquid collection tank 1 and the concentration device 3. The chlorine removing device 10 removes chlorine by a method such as an electrolysis method, an electrodialysis method, or an adsorption method.

【0015】しかして、上記第1の実施の形態におい
て、廃液収集タンク1に収集した廃液を廃液移送ライン
2から流して濃縮装置3に移送し濃縮する。濃縮装置3
で蒸発した蒸留水4は分離され、濃縮された濃縮廃液は
前記所定値により、濃縮廃液排出ライン5を通り、濃縮
廃液タンク6へ排出される。
Therefore, in the first embodiment, the waste liquid collected in the waste liquid collection tank 1 is flown from the waste liquid transfer line 2 and transferred to the concentrating device 3 to be concentrated. Concentrator 3
The distilled water 4 evaporated in (1) is separated, and the concentrated concentrated waste liquid is discharged to the concentrated waste liquid tank 6 through the concentrated waste liquid discharge line 5 according to the predetermined value.

【0016】排出された濃縮廃液の固形分濃度または硫
酸ナトリウム濃度が前記所定値に達していない場合、濃
縮廃液タンク6内の濃縮廃液は濃縮廃液分岐ライン9を
通し塩素除去装置10に移送して塩素を除去する。塩素除
去後の濃縮廃液は濃縮廃液戻しライン11を経て、再度濃
縮装置3で濃縮され、固形分濃度または硫酸ナトリウム
濃度が所定値に達した場合、濃縮廃液タンク6に移送し
て固化装置8で固化処理される。
When the solid content concentration or the sodium sulfate concentration of the discharged concentrated waste liquid has not reached the predetermined value, the concentrated waste liquid in the concentrated waste liquid tank 6 is transferred to the chlorine removing device 10 through the concentrated waste liquid branch line 9. Remove chlorine. The concentrated waste liquid after chlorine removal is concentrated again in the concentrating device 3 via the concentrated waste liquid returning line 11, and when the solid content concentration or the sodium sulfate concentration reaches a predetermined value, it is transferred to the concentrated waste liquid tank 6 and the solidifying device 8 is used. Solidified.

【0017】この場合、塩素除去装置10で塩素除去後の
濃縮廃液を破線で示す濃縮廃液タンク戻しライン12を通
して一旦濃縮廃液タンク6に戻した後、濃縮廃液タンク
6から濃縮装置戻しライン13を通し濃縮装置3へ移送し
て再度濃縮処理してもよい。また、塩素除去装置10で塩
素除去後の濃縮廃液を破線で示す廃液戻しライン14を通
し廃液収集タンク1に戻して他の収集した廃液ととも
に、再度濃縮処理することもできる。
In this case, the concentrated waste liquid after chlorine removal by the chlorine removal device 10 is once returned to the concentrated waste liquid tank 6 through the concentrated waste liquid tank return line 12 shown by a broken line, and then the concentrated waste liquid tank 6 is passed through the concentrator return line 13 It may be transferred to the concentrating device 3 and concentrated again. Further, the concentrated waste liquid after chlorine removal by the chlorine removal device 10 can be returned to the waste liquid collection tank 1 through a waste liquid return line 14 indicated by a broken line, and can be concentrated again with other collected waste liquids.

【0018】本実施の形態によれば濃縮廃液中の塩素を
除去することにより、濃縮度を高め、再度濃縮可能な廃
液とすることにより、濃縮廃液の発生量を低減でき、設
備の効率的な運用が可能となる。
According to the present embodiment, by removing chlorine in the concentrated waste liquid, the degree of concentration can be increased, and the waste liquid can be concentrated again, so that the amount of the concentrated waste liquid generated can be reduced and the efficiency of the equipment can be improved. Operation becomes possible.

【0019】つぎに図2により本発明に係る放射性廃液
処理装置の第2の実施の形態について説明する。なお、
図2中、図1と同一部分には同一符号を付して重複する
部分の説明は省略する。本実施の形態が第1の実施の形
態と異なる部分は廃液収集タンク1と濃縮装置3を接続
する廃液移送ライン2から分岐して廃液分岐ライン15を
接続し、この廃液分岐ライン15を塩素除去装置10に接続
し、この塩素除去装置10と廃液収集タンク1の間を廃液
戻しライン14で接続したことにある。
Next, a second embodiment of the radioactive liquid waste treatment apparatus according to the present invention will be described with reference to FIG. In addition,
2, the same parts as those in FIG. 1 are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. This embodiment is different from the first embodiment in that the waste liquid transfer line 2 connecting the waste liquid collection tank 1 and the concentrator 3 is branched to connect the waste liquid branch line 15, and the waste liquid branch line 15 is used for chlorine removal. This is because it is connected to the device 10, and the chlorine removal device 10 and the waste liquid collection tank 1 are connected by a waste liquid return line 14.

【0020】しかして、本実施の形態において、廃液収
集タンク1に収集した廃液は廃棄濃縮装置3へ移送して
濃縮する前の廃液分岐ライン15から分流し塩素除去装置
10に移送して塩素を除去する。塩素除去後の廃液は廃液
戻しライン14を経て廃液収集タンク1に戻し、濃縮装置
3で濃縮処理する。
In the present embodiment, however, the waste liquid collected in the waste liquid collection tank 1 is branched from the waste liquid branch line 15 before being transferred to the waste concentrating device 3 and concentrated, and the chlorine removing device is provided.
Transfer to 10 to remove chlorine. The waste liquid from which chlorine has been removed is returned to the waste liquid collection tank 1 via the waste liquid returning line 14 and concentrated in the concentrating device 3.

【0021】この時、塩素除去装置10で塩素除去後の廃
液を破線で示す直接戻しライン16を通し直接濃縮装置3
へ移送して濃縮処理してもよい。本実施の形態によれば
廃液収集タンク1に収集した廃液中の塩素を除去するこ
とにより、濃縮装置3での濃縮度を高めることができ
る。
At this time, the waste liquid after chlorine removal by the chlorine removal device 10 is passed through a direct return line 16 shown by a broken line to directly condense the device 3.
It may be transferred to and concentrated. According to the present embodiment, by removing chlorine in the waste liquid collected in the waste liquid collection tank 1, the degree of concentration in the concentration device 3 can be increased.

【0022】つぎに図3により本発明に係る放射性廃液
処理装置の第3の実施の形態について説明する。なお、
図3中、図1と同一部分には同一符号を付して重複する
部分の説明は省略する。
Next, a third embodiment of the radioactive liquid waste treatment apparatus according to the present invention will be described with reference to FIG. In addition,
3, those parts that are the same as those corresponding parts in FIG. 1 are designated by the same reference numerals, and a description of the overlapping parts will be omitted.

【0023】本実施の形態が第1の実施の形態と異なる
部分は濃縮装置3の濃縮廃液排出ライン5から分岐して
塩素除去装置10に接続する分岐ライン17を設けて濃縮廃
液中の塩素を除去する塩素除去装置10に直接流入すると
ともに、この塩素除去装置10と廃液移送ライン2の間を
濃縮廃液戻しライン11で接続したことにある。
The part of the present embodiment different from the first embodiment is to install a branch line 17 that branches from the concentrated waste liquid discharge line 5 of the concentrating device 3 and connects to the chlorine removing device 10 to remove chlorine in the concentrated waste liquid. This is because it directly flows into the chlorine removing device 10 for removal, and the chlorine removing device 10 and the waste liquid transfer line 2 are connected by the concentrated waste liquid returning line 11.

【0024】しかして、本実施の形態において、廃液収
集タンク1に収集した廃液は廃液移送ライン2を経て濃
縮装置3に移送し濃縮する。濃縮装置3で濃縮された濃
縮廃液は分岐ライン17から塩素除去装置10に流入し、こ
の塩素除去装置10により、塩素が除去され濃縮廃液戻し
ライン11を介して、濃縮装置3へ戻される。
Therefore, in the present embodiment, the waste liquid collected in the waste liquid collection tank 1 is transferred to the concentrating device 3 via the waste liquid transfer line 2 and concentrated. The concentrated waste liquid concentrated in the concentrating device 3 flows into the chlorine removing device 10 from the branch line 17, the chlorine is removed by the chlorine removing device 10, and is returned to the concentrating device 3 via the concentrated waste liquid returning line 11.

【0025】この時、塩素除去装置10で塩素除去後の濃
縮廃液を廃液戻しライン14を通し廃液収集タンク1に戻
して他の収集した廃液と共に再度濃縮処理してもよい。
本実施の形態によれば濃縮装置内の濃縮廃液中の塩素を
除去することにより、濃縮度を高めることができる。
At this time, the concentrated waste liquid from which chlorine has been removed by the chlorine removing device 10 may be returned to the waste liquid collecting tank 1 through the waste liquid returning line 14 and concentrated again with other collected waste liquids.
According to the present embodiment, the concentration can be increased by removing chlorine in the concentrated waste liquid in the concentrator.

【0026】なお、塩素除去装置における塩素除去方法
としては濃縮廃液の性状により電気分解法,電気透析
法,吸着法などを適宜選択し、いずれの方法を用いた装
置とすることもできる。
As the chlorine removing method in the chlorine removing apparatus, an electrolysis method, an electrodialysis method, an adsorption method or the like may be appropriately selected depending on the properties of the concentrated waste liquid, and any method may be used.

【0027】[0027]

【発明の効果】本発明装置によれば、濃縮装置で濃縮し
た廃液中の塩素成分を除去することにより、再度濃縮処
理が可能となる。また、廃液収集タンクで収集した廃液
中の塩素成分を除去することにより、濃縮装置での濃縮
度を上げることが可能となる。そのため、廃棄物として
発生する濃縮廃液の発生量を低減することができ、設備
の効率的な運用が可能となる。
According to the apparatus of the present invention, the concentration process can be performed again by removing the chlorine component in the waste liquid concentrated by the concentration apparatus. Further, by removing the chlorine component in the waste liquid collected in the waste liquid collection tank, it becomes possible to increase the degree of concentration in the concentrator. Therefore, the amount of concentrated waste liquid generated as waste can be reduced, and the equipment can be operated efficiently.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明に係る放射性廃液処理装置の第1の実施
の形態を示す流れ線図。
FIG. 1 is a flow diagram showing a first embodiment of a radioactive liquid waste treatment apparatus according to the present invention.

【図2】本発明に係る放射性廃液処理装置の第2の実施
の形態を示す流れ線図。
FIG. 2 is a flow chart showing a second embodiment of the radioactive liquid waste treatment apparatus according to the present invention.

【図3】本発明に係る放射性廃液処理装置の第3の実施
の形態を示す流れ線図。
FIG. 3 is a flow chart showing a third embodiment of the radioactive liquid waste treatment apparatus according to the present invention.

【図4】従来の放射性廃液処理装置を示す流れ線図。FIG. 4 is a flow diagram showing a conventional radioactive waste liquid treatment device.

【符号の説明】[Explanation of symbols]

1…廃液収集タンク、2…廃液移送ライン、3…濃縮装
置、4…蒸留水、5…濃縮廃液排出ライン、6…濃縮廃
液タンク、7…濃縮廃液移送ライン、8…固化装置、9
…濃縮廃液分岐ライン、10…塩素除去装置、11…脱塩素
濃縮廃液戻しライン、12…濃縮廃液タンク戻しライン、
13…濃縮装置戻しライン、14…廃液戻しライン、15…廃
液分岐ライン、16…直接戻しライン、17…分岐ライン。
1 ... Waste liquid collection tank, 2 ... Waste liquid transfer line, 3 ... Concentrator, 4 ... Distilled water, 5 ... Concentrated waste liquid discharge line, 6 ... Concentrated waste liquid tank, 7 ... Concentrated waste liquid transfer line, 8 ... Solidifying device, 9
… Concentrated waste liquid branch line, 10… Chlorine removal device, 11… Dechlorination concentrated waste liquid return line, 12… Concentrated waste liquid tank return line,
13 ... Concentrator return line, 14 ... Waste liquid return line, 15 ... Waste liquid branch line, 16 ... Direct return line, 17 ... Branch line.

Claims (5)

【特許請求の範囲】[Claims] 【請求項1】 原子力発電所で発生する放射性廃液を収
集する廃液収集タンクと、この収集タンク内の廃液を濃
縮する濃縮装置と、この濃縮装置で濃縮した濃縮廃液を
貯蔵する濃縮廃液タンクと、この濃縮廃液タンク内の濃
縮廃液中の塩素を除去する塩素除去装置と、この塩素除
去装置で塩素除去後の濃縮廃液を前記濃縮装置へ戻す濃
縮廃液戻しラインとを具備したことを特徴とする放射性
廃液処理装置。
1. A waste liquid collection tank for collecting radioactive waste liquid generated in a nuclear power plant, a concentrating device for concentrating the waste liquid in the collection tank, and a concentrated waste liquid tank for storing the concentrated waste liquid concentrated by the concentrating device. A radioactive substance characterized by comprising a chlorine removing device for removing chlorine in the concentrated waste liquid in the concentrated waste liquid tank, and a concentrated waste liquid returning line for returning the concentrated waste liquid after chlorine removal by the chlorine removing device to the concentrating device. Waste liquid treatment equipment.
【請求項2】 前記塩素除去装置で塩素除去後の濃縮廃
液を一旦濃縮廃液タンクに戻す戻しラインを設けるとと
もに、前記濃縮廃液タンクから濃縮装置へ戻す濃縮廃液
戻しラインを設けてなることを特徴とする請求項1記載
の放射性廃液処理装置。
2. A concentration waste liquid return line for returning the concentrated waste liquid after chlorine removal in the chlorine removal device to the concentrated waste liquid tank, and a concentrated waste liquid return line returning from the concentrated waste liquid tank to the concentration device are provided. The radioactive waste liquid treatment apparatus according to claim 1.
【請求項3】 前記塩素除去装置で塩素除去後の濃縮廃
液を前記廃液収集タンクへ戻す廃液戻しラインを設けて
なることを特徴とする請求項1記載の放射性廃液処理装
置。
3. The radioactive waste liquid treatment apparatus according to claim 1, further comprising a waste liquid return line for returning the concentrated waste liquid after chlorine removal by the chlorine removal device to the waste liquid collection tank.
【請求項4】 原子力発電所で発生する放射性廃液を収
集する廃液収集タンクと、この収集タンク内の廃液を濃
縮する濃縮装置と、この濃縮装置と前記廃液収集タンク
とを接続する廃液移送ラインから分岐して設けられた前
記廃液中の塩素を除去する塩素除去装置と、この塩素除
去装置で塩素除去後の廃液を廃棄収集タンクへ戻す戻し
ラインとを具備したことを特徴とする放射性廃液処理装
置。
4. A waste liquid collecting tank for collecting radioactive waste liquid generated in a nuclear power plant, a concentrating device for concentrating the waste liquid in the collecting tank, and a waste liquid transfer line connecting the concentrating device and the waste liquid collecting tank. A radioactive waste liquid treatment apparatus comprising: a branching chlorine removal device for removing chlorine in the waste liquid; and a return line for returning the waste liquid after chlorine removal by the chlorine removal device to a waste collection tank. .
【請求項5】 原子力発電所で発生する放射性廃液を収
集する廃液収集タンクと、この収集タンク内の廃液を濃
縮する濃縮装置と、この濃縮装置内の濃縮廃液中の塩素
を除去する塩素除去装置と、この塩素除去装置で塩素除
去後の濃縮廃液を前記濃縮装置へ戻す濃縮廃液戻しライ
ンとを具備したことを特徴とする放射性廃液処理装置。
5. A waste liquid collection tank for collecting radioactive waste liquid generated in a nuclear power plant, a concentrating device for concentrating the waste liquid in the collection tank, and a chlorine removing device for removing chlorine in the concentrated waste liquid in the concentrating device. And a concentrated waste liquid return line for returning the concentrated waste liquid after chlorine removal by the chlorine removal device to the concentration device.
JP274796A 1996-01-11 1996-01-11 Radioactive waste liquid treatment device Pending JPH09189798A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP274796A JPH09189798A (en) 1996-01-11 1996-01-11 Radioactive waste liquid treatment device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP274796A JPH09189798A (en) 1996-01-11 1996-01-11 Radioactive waste liquid treatment device

Publications (1)

Publication Number Publication Date
JPH09189798A true JPH09189798A (en) 1997-07-22

Family

ID=11537951

Family Applications (1)

Application Number Title Priority Date Filing Date
JP274796A Pending JPH09189798A (en) 1996-01-11 1996-01-11 Radioactive waste liquid treatment device

Country Status (1)

Country Link
JP (1) JPH09189798A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013148364A (en) * 2012-01-17 2013-08-01 Mitsubishi Heavy Ind Ltd Radioactive waste liquid processor
JP2013148365A (en) * 2012-01-17 2013-08-01 Mitsubishi Heavy Ind Ltd Radioactive waste liquid processor
JP2013148366A (en) * 2012-01-17 2013-08-01 Mitsubishi Heavy Ind Ltd Radioactive waste liquid processing apparatus
CN105006263A (en) * 2015-06-19 2015-10-28 华东理工大学 Method for treating nuclear power plant radioactive liquid waste by generating manganous-manganic oxide in situ

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013148364A (en) * 2012-01-17 2013-08-01 Mitsubishi Heavy Ind Ltd Radioactive waste liquid processor
JP2013148365A (en) * 2012-01-17 2013-08-01 Mitsubishi Heavy Ind Ltd Radioactive waste liquid processor
JP2013148366A (en) * 2012-01-17 2013-08-01 Mitsubishi Heavy Ind Ltd Radioactive waste liquid processing apparatus
CN105006263A (en) * 2015-06-19 2015-10-28 华东理工大学 Method for treating nuclear power plant radioactive liquid waste by generating manganous-manganic oxide in situ

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