JPH07209489A - Radioactive waste solution disposing device - Google Patents
Radioactive waste solution disposing deviceInfo
- Publication number
- JPH07209489A JPH07209489A JP6004396A JP439694A JPH07209489A JP H07209489 A JPH07209489 A JP H07209489A JP 6004396 A JP6004396 A JP 6004396A JP 439694 A JP439694 A JP 439694A JP H07209489 A JPH07209489 A JP H07209489A
- Authority
- JP
- Japan
- Prior art keywords
- chlorine
- waste solution
- waste liquid
- waste
- hcw
- 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
Landscapes
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
- Water Treatment By Electricity Or Magnetism (AREA)
- Treatment Of Water By Ion Exchange (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は放射性廃液処理装置に係
り、特に、原子力発電所などの放射性廃液を蒸発濃縮処
理する施設に好適な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, and more particularly to a radioactive liquid waste treatment apparatus suitable for facilities for evaporative concentration of radioactive liquid waste such as nuclear power plants.
【０００２】[0002]
【従来の技術】原子力発電所では、放射性廃液の処理に
よって水がリサイクルされている。図２に原子力発電所
の廃液処理のブロック図を示す。原子力発電所で発生す
る放射性廃液は、二つの種類に分けられて処理される。
すなわち、高電導度廃液(HCW）と低電導度廃液（ＬＣ
Ｗ）である。前者は、復水脱塩器の再生廃液，化学処理
廃液，床ドレンなどで、種々のイオンを含む電導度の高
い廃液である。後者は、主として機器のドレン水で、イ
オンをほとんど含まない電導度の低い廃液である。この
うち、高電導度廃液は、蒸発濃縮器によって処理され、
所定の濃度まで濃縮される。蒸発濃縮器は「化学工学便
覧 改訂４版」（化学工学協会編，丸善，昭和５３年発
行）に示されており、蒸発濃縮操作によって、濃縮液と
凝縮水が発生する。濃縮廃液は、固化系に移送され、セ
メントなどを用いて直接固化されるか、減容処理された
後に固化されて放射性廃棄物固化体となるが、凝縮水は
イオン交換処理されて再利用される。一方、低電導度廃
液は、ろ過，イオン交換処理され、再利用される。2. Description of the Related Art In a nuclear power plant, water is recycled by treating radioactive liquid waste. Fig. 2 shows a block diagram of waste liquid treatment at a nuclear power plant. The radioactive liquid waste generated at a nuclear power plant is divided into two types and processed.
That is, high conductivity waste liquid (HCW) and low conductivity waste liquid (LC
W). The former is a reclaimed wastewater from a condensate demineralizer, a chemical treatment wastewater, a floor drain, and the like, which is a wastewater containing various ions and having high conductivity. The latter is mainly drain water of equipment and is a waste liquid of low electric conductivity containing almost no ions. Of these, the high-conductivity waste liquid is processed by the evaporative concentrator,
It is concentrated to a predetermined concentration. The evaporative concentrator is shown in "Chemical Engineering Handbook, 4th Edition" (edited by the Chemical Engineering Society of Japan, Maruzen, published in 1978), and concentrate and condensed water are generated by evaporative concentration operation. The concentrated waste liquid is transferred to a solidification system and either directly solidified using cement or the like, or volume-reduced and then solidified into radioactive waste solidified, but the condensed water is ion-exchanged and reused. It On the other hand, the low-conductivity waste liquid is filtered, ion-exchanged, and reused.
【０００３】近年、原子力発電所の信頼性が向上し、復
水器での海水リークが無くなったため、復水脱塩器の再
生の必要が無くなってきた。この結果、高電導度廃液の
主要な発生源であり、濃度の高い復水脱塩器からの再生
廃液の発生が無くなってきた。In recent years, the reliability of nuclear power plants has improved and seawater leaks in condensers have disappeared, so there is no longer any need to regenerate the condensate demineralizer. As a result, the generation of recycled waste liquid from the highly concentrated condensate demineralizer, which is the main source of high conductivity waste liquid, has disappeared.
【０００４】[0004]
【発明が解決しようとする課題】従来の蒸発濃縮器で
は、高電導度廃液の主要な発生源が復水脱塩器からの高
濃度の再生廃液であることに基づき設計されているた
め、近年の原子力発電所の信頼性向上が、効果的に放射
性廃棄物固化体の減少に反映されないという問題点があ
る。すなわち、従来の蒸発濃縮器では高電導度廃液を所
定の濃度まで濃縮できないという問題がある。In the conventional evaporative concentrator, since the main source of the high-conductivity waste liquid is the high-concentration regenerated waste liquid from the condensate demineralizer, it has been designed in recent years. There is a problem that the improvement of the reliability of the nuclear power plant is not effectively reflected in the reduction of the solidified radioactive waste. That is, the conventional evaporative concentrator has a problem that the high-conductivity waste liquid cannot be concentrated to a predetermined concentration.
【０００５】本発明の目的は、蒸発濃縮器の問題点であ
る濃縮液の濃度が上げられない理由を明らかにし、その
解決手段を提供することにある。An object of the present invention is to clarify the reason why the concentration of the concentrated liquid, which is a problem of the evaporative concentrator, cannot be increased, and to provide a means for solving the problem.
【０００６】[0006]
【課題を解決するための手段】上記の目的を達成するた
め、本発明は放射性廃液を蒸発濃縮する放射性廃液処理
装置が、放射性廃液中の塩素を除去する塩素除去装置
と、前記廃液を蒸発濃縮する濃縮器とを含み、前記塩素
除去装置を他の装置から発生する廃棄物に吸着させる吸
着装置とした。In order to achieve the above object, the present invention provides a radioactive liquid waste treatment apparatus for evaporative concentration of radioactive liquid waste, a chlorine removing device for removing chlorine in the radioactive liquid waste, and an evaporative concentration of the liquid waste. And a concentrator for controlling the chlorine removal device to adsorb waste generated from another device.
【０００７】上記の目的を達成するため、本発明は放射
性廃液を蒸発濃縮する放射性廃液処理装置が、放射性廃
液中の塩素を除去する塩素除去装置と、前記廃液を蒸発
濃縮する濃縮器とを含み、前記塩素除去装置を塩素を気
体として除去する装置とした。To achieve the above object, the present invention provides a radioactive liquid waste treatment apparatus for evaporating and concentrating a radioactive liquid waste, including a chlorine removing device for removing chlorine in the radioactive liquid waste, and a concentrator for evaporating and concentrating the liquid waste. The chlorine removing device is a device for removing chlorine as a gas.
【０００８】[0008]
【作用】従来技術の蒸発濃縮器の濃縮液の濃度が上げら
れない理由が、廃液中の塩素イオンであるため、本発明
は塩素イオンをあらかじめ除去するようにしたものであ
る。また、本発明は、塩素イオンの除去に当っては、使
用済の廃棄物を利用、あるいは、塩素を気体として除去
することによって、廃棄物固化体の発生量の増加を抑制
したものである。The reason why the concentration of the concentrated liquid in the conventional evaporative concentrator cannot be increased is that chlorine ions are contained in the waste liquid. Therefore, the present invention removes the chlorine ions in advance. In addition, the present invention suppresses an increase in the amount of solid waste produced by utilizing a used waste or removing chlorine as a gas when removing chlorine ions.
【０００９】[0009]
【実施例】以下、本発明の好適な実施例について、図面
を用いて詳細に説明する。Preferred embodiments of the present invention will be described in detail below with reference to the drawings.
【００１０】（実施例１）図１に本発明の好適な実施例
の廃液処理のブロック図を示す。ここでは、使用済みイ
オン交換樹脂を利用した例を示すが、本発明はこれに限
定されることは無く、他の塩素イオンを吸着する廃棄物
であっても良い。本実施例は、濃縮器の前段に塩素イオ
ン除去装置を設置したものである。ＨＣＷの脱塩器、お
よびＬＣＷの脱塩器の使用済みイオン交換樹脂を塩素イ
オン除去装置に移送し、濃縮器に流入するＨＣＷ中の塩
素イオンを除去する。ＨＣＷは、発生量が年間２０００
ｔ，塩素イオン濃度が５００ｇ／ｔであり、ＨＣＷの脱
塩器、およびＬＣＷの脱塩器での年間のイオン交換樹脂
の使用量が３ｔと想定する。通常、脱塩器でのイオン交
換樹脂の半分が、塩素イオンを除去できる陰イオン交換
樹脂である。また、希薄な濃度の放射性物質を高い除去
効率で除去するため、イオン交換樹脂のイオン交換容量
（高イオン濃度で吸着できるイオン量の最大値）の半分
しか使用されない状態で廃棄されている。(Embodiment 1) FIG. 1 shows a block diagram of waste liquid treatment of a preferred embodiment of the present invention. Here, an example in which a used ion exchange resin is used is shown, but the present invention is not limited to this, and may be waste that adsorbs other chlorine ions. In this embodiment, a chlorine ion removing device is installed before the concentrator. The used ion-exchange resin of the HCW demineralizer and the LCW demineralizer is transferred to a chlorine ion removal device to remove chlorine ions in the HCW flowing into the concentrator. The amount of HCW generated is 2000 per year
t, chlorine ion concentration is 500 g / t, and it is assumed that the annual amount of ion exchange resin used in the HCW demineralizer and the LCW demineralizer is 3 t. Usually, half of the ion exchange resin in the desalting device is an anion exchange resin capable of removing chloride ions. Further, in order to remove a dilute concentration of radioactive substances with high removal efficiency, only half of the ion exchange capacity (the maximum value of the amount of ions that can be adsorbed at a high ion concentration) of the ion exchange resin is used and discarded.
【００１１】本実施例は、イオン交換容量が残っている
イオン交換樹脂を利用するものである。本実施例では、
図１に示すように、ＨＣＷは、使用済みイオン交換樹脂
が充填された塩素イオン除去装置を通る。ここで、除去
される塩素イオン量は、次のようにして算出できる。除
去できる塩素イオン量（kg／ｙ）は、イオン交換樹脂の
使用量（３ｔ／ｙ）×陰イオン交換樹脂の割合（０.５)
×新品の陰イオン交換樹脂の塩素イオンに対するイオン
交換容量（７０kg／ｔ）×イオン交換容量の残留割合
(０.５）で計算でき、５３kg／ｙとなる。一方、廃液中
の塩素イオン量（kg／ｙ）は、廃液発生量（２０００ｔ
／ｙ）×廃液中の塩素イオン濃度（500ｇ／ｔ）で計算
でき、１００kg／ｙとなる。したがって、廃液中の塩素
イオン量の約半分をＨＣＷおよびＬＣＷ脱塩器の使用済
みイオン交換樹脂で除去できる。さらに、復水脱塩器の
使用済みイオン交換樹脂を利用することで、廃液中の塩
素イオン量の９０％以上が除去できる。したがって、濃
縮器での上限の塩素イオン濃度が５０００ないし５００
００ｇ／ｔであるため、従来は最大百倍程度の濃縮しか
できなかったが、本実施例では一千倍以上の濃縮が可能
となる。The present embodiment utilizes an ion exchange resin having a remaining ion exchange capacity. In this embodiment,
As shown in FIG. 1, the HCW passes through a chlorine ion removing device filled with a used ion exchange resin. Here, the amount of chlorine ions removed can be calculated as follows. Chlorine ion amount (kg / y) that can be removed is the amount of ion exchange resin used (3 t / y) x ratio of anion exchange resin (0.5)
× Ion exchange capacity of new anion exchange resin for chlorine ions (70 kg / t) × Residual ratio of ion exchange capacity
It can be calculated with (0.5), which is 53 kg / y. On the other hand, the chlorine ion amount (kg / y) in the waste liquid is the waste liquid generation amount (2000 t
/ Y) x chlorine ion concentration in the waste liquid (500 g / t), which is 100 kg / y. Therefore, about half of the chlorine ion amount in the waste liquid can be removed by the used ion exchange resin of the HCW and LCW desalting unit. Furthermore, by using the used ion exchange resin of the condensate demineralizer, 90% or more of the chlorine ion amount in the waste liquid can be removed. Therefore, the upper limit chlorine ion concentration in the concentrator is 5000 to 500.
Since the concentration is 00 g / t, conventionally, the maximum concentration was about 100 times, but in the present embodiment, the concentration can be 1,000 times or more.
【００１２】本実施例によれば、ＨＣＷの濃縮廃液の発
生量を１０％にでき、廃棄物固化体の発生量を低減でき
る。According to this embodiment, the amount of HCW concentrated waste liquid generated can be reduced to 10%, and the amount of waste solidified products can be reduced.
【００１３】（実施例２）図３に本発明の好適な他の実
施例の廃液処理のブロック図を示す。ここでは、電解に
よって塩素イオンを気体として除去するが、本発明はこ
れに限定されることは無く、酸化剤を添加する方法など
を用いても良い。本実施例では、濃縮器の前段に塩素イ
オン電解装置を設置したものである。したがって、ＨＣ
Ｗは、一度タンクに集められた後、塩素イオン電解装置
を通り、濃縮器に送られる。塩素イオン電解装置では、
陽極と陰極の二種類の電極があるが、陽極上で発生する
次の反応によって、塩素イオンが塩素ガスとなる。２Ｃ
ｌ-−２ｅ→Ｃｌ2↑発生した塩素ガスは、気相に移り、
排ガスとして排気系より放出される。したがって、本実
施例によれば、廃液中の塩素イオン濃度を１０％以下に
低減でき、従来は百倍程度の濃縮しかできなかったＨＣ
Ｗが、一千倍以上の濃縮が可能となる。(Embodiment 2) FIG. 3 shows a block diagram of waste liquid treatment of another preferred embodiment of the present invention. Here, chlorine ions are removed as a gas by electrolysis, but the present invention is not limited to this, and a method of adding an oxidizing agent or the like may be used. In this embodiment, a chlorine ion electrolysis device is installed in the preceding stage of the concentrator. Therefore, HC
After W is once collected in the tank, it passes through the chloride ion electrolyzer and is sent to the concentrator. In the chlorine ion electrolysis device,
There are two types of electrodes, an anode and a cathode, but the chlorine ion becomes chlorine gas by the following reaction that occurs on the anode. 2C
l - -2e → Cl 2 ↑ generated chlorine gas is transferred to the gas phase,
It is released from the exhaust system as exhaust gas. Therefore, according to the present embodiment, the concentration of chlorine ions in the waste liquid can be reduced to 10% or less, and the concentration of HC which has been conventionally only about 100 times higher.
W can be concentrated 1,000 times or more.
【００１４】本実施例によれば、上記実施例１と同様
に、ＨＣＷの濃縮廃液の発生量を１０％にでき、廃棄物
固化体の発生量を低減できる。According to this embodiment, as in the case of Embodiment 1, the amount of concentrated waste liquid of HCW can be reduced to 10% and the amount of solid waste can be reduced.
【００１５】[0015]
【発明の効果】本発明によれば、プラントの信頼性向上
に伴って変化する廃液の性状変動に対応でき、効果的に
廃棄物発生量を低減できる。すなわち、高電導度廃液用
の濃縮器の腐食の原因となる塩素イオンを除去でき、廃
液を高い濃度まで濃縮できるため、濃縮廃液の発生量を
１０％以下に低減できる。According to the present invention, it is possible to cope with the change in the property of the waste liquid that changes with the improvement of the reliability of the plant, and it is possible to effectively reduce the amount of waste generated. That is, since chlorine ions that cause corrosion of the concentrator for high-conductivity waste liquid can be removed and the waste liquid can be concentrated to a high concentration, the amount of concentrated waste liquid generated can be reduced to 10% or less.
【図１】本発明の一実施例の廃液処理のブロック図。FIG. 1 is a block diagram of waste liquid treatment according to an embodiment of the present invention.
【図２】原子力発電所の廃液処理の従来のブロック図。FIG. 2 is a conventional block diagram of waste liquid treatment of a nuclear power plant.
【図３】本発明の好適な他の実施例の廃液処理のブロッ
ク図。FIG. 3 is a block diagram of waste liquid treatment according to another preferred embodiment of the present invention.
Claims (2)
装置において、前記放射性廃液中の塩素を除去する塩素
除去装置と、前記放射性廃液を蒸発濃縮する濃縮器とを
含み、前記塩素除去装置が他の装置から発生する前記放
射性廃棄物に吸着させる吸着装置であることを特徴とす
る放射性廃液処理装置。1. A radioactive waste liquid treatment apparatus for evaporating and concentrating radioactive waste liquid, comprising: a chlorine removing device for removing chlorine in the radioactive waste liquid; and a concentrator for evaporating and concentrating the radioactive waste liquid. A radioactive waste liquid treatment device which is an adsorption device for adsorbing the radioactive waste generated from the device.
装置において、前記放射性廃液中の塩素を除去する塩素
除去装置と、前記放射性廃液を蒸発濃縮する濃縮器とを
含み、前記塩素除去装置が塩素を気体として除去する装
置であることを特徴とする放射性廃液処理装置。2. A radioactive waste liquid treatment device for evaporating and concentrating radioactive waste liquid, comprising: a chlorine removing device for removing chlorine in the radioactive waste liquid; and a concentrator for evaporating and concentrating the radioactive waste liquid, wherein the chlorine removing device comprises chlorine. An apparatus for treating radioactive waste liquid, which is an apparatus for removing as a gas.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6004396A JPH07209489A (en) | 1994-01-20 | 1994-01-20 | Radioactive waste solution disposing device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6004396A JPH07209489A (en) | 1994-01-20 | 1994-01-20 | Radioactive waste solution disposing device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH07209489A true JPH07209489A (en) | 1995-08-11 |
Family
ID=11583192
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP6004396A Pending JPH07209489A (en) | 1994-01-20 | 1994-01-20 | Radioactive waste solution disposing device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH07209489A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013148366A (en) * | 2012-01-17 | 2013-08-01 | Mitsubishi Heavy Ind Ltd | Radioactive waste liquid processing apparatus |
| JP2013148365A (en) * | 2012-01-17 | 2013-08-01 | Mitsubishi Heavy Ind Ltd | Radioactive waste liquid processor |
-
1994
- 1994-01-20 JP JP6004396A patent/JPH07209489A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013148366A (en) * | 2012-01-17 | 2013-08-01 | Mitsubishi Heavy Ind Ltd | Radioactive waste liquid processing apparatus |
| JP2013148365A (en) * | 2012-01-17 | 2013-08-01 | Mitsubishi Heavy Ind Ltd | Radioactive waste liquid processor |
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