JPH05323095A - Processing method for decontamination waste liquid - Google Patents

Processing method for decontamination waste liquid

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Publication number
JPH05323095A
JPH05323095A JP12727992A JP12727992A JPH05323095A JP H05323095 A JPH05323095 A JP H05323095A JP 12727992 A JP12727992 A JP 12727992A JP 12727992 A JP12727992 A JP 12727992A JP H05323095 A JPH05323095 A JP H05323095A
Authority
JP
Japan
Prior art keywords
waste liquid
decontamination
acid
waste
treatment
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.)
Withdrawn
Application number
JP12727992A
Other languages
Japanese (ja)
Inventor
Masami Toda
正見 遠田
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 Corp
Original Assignee
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 Corp filed Critical Toshiba Corp
Priority to JP12727992A priority Critical patent/JPH05323095A/en
Publication of JPH05323095A publication Critical patent/JPH05323095A/en
Withdrawn legal-status Critical Current

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Abstract

PURPOSE:To reduce the radioactive secondary waste generation by oxidizing the trivallent Ce in decontamination waste liquid to quadrivallent Ce with electrolytic oxidation, separating the quadrivallent Ce and acid from the processed decontamination waste liquid and reusing it. CONSTITUTION:Decontamination waste liquid 11 is oxidized by electrolysis 12 to raise the concentration of Ce<4+> in the decontamination waste liquid and the waste liquid and dialysis liquid 14 are passed by water through a negative ion exchanger film 15. Then, the acid in the waste liquid 11 and Ce<4+> having formed complex negative ion move through the exchanger film to the dialysis liquid and are recovered as recovery solution 16. The recovery solution after controlling 17 concentration is reused as decontamination liquid. On the other hand, a little Ce<4+> remains in the processed waste liquid 19 eliminated of acid and Ce<4+> and therefore, by adding hydrogen peroxide to reduce in process 20 to be chemically stable Ce<4+>. The reduction processed 18 process waste liquid 19 is neutralized in process 21 with sodiumhydrate solution and dried and solidified 22 sludge and sodium salt are stored as radioactive waste.

Description

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

【0001】[0001]

【産業上の利用分野】本発明は放射性金属廃棄物を除染
した後に発生する使用済み酸性除染液を再生するための
除染廃液の処理方法に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating a decontamination waste liquid for regenerating a used acidic decontamination liquid generated after decontaminating radioactive metal waste.

【0002】[0002]

【従来の技術】例えば原子力発電設備の廃止・解体措置
にともなって発生する放射能に汚染された金属廃棄物
は、放射能を除去した後、保管・再利用等を行うべく廃
棄処分が行われる。
2. Description of the Related Art For example, radioactive waste-contaminated metal waste generated by the abolition and dismantling of nuclear power generation facilities is disposed of after being removed and stored and reused. ..

【0003】ここで、放射能汚染された金属廃棄物の除
染を行う手段としては、セリウム3価イオン(Ce3+
とセリウム4価イオン(Ce4+)とを含む酸性の除染液
(以下レドックス除染液という)を用いて、電解酸化反
応によってCe3+からCe4+を生成し、このCe4+の酸
化力を利用して金属廃棄物表面から放射性物質を除去す
る除染方法が知られている。
Here, as means for decontaminating radioactively contaminated metal waste, cerium trivalent ions (Ce 3+ )
And using cerium tetravalent ions (Ce 4+) and decontamination liquid acidic containing (hereinafter referred redox decontamination liquid), produces a Ce 4+ from Ce 3+ by electrolytic oxidation reaction of the Ce 4+ A decontamination method is known in which radioactive substances are removed from the surface of metal waste by utilizing the oxidizing power.

【0004】このレドックス除染液による処理は、例え
ば図3に示すようなレドックス除染装置を用いて行われ
る。図3において、符号1は電解槽、符号2は除染槽で
あり、この電解槽1内と除染槽2内には除染剤であるC
3+とCe4+を溶解させた酸性のレドックス除染液3が
貯留されている。また電解槽1には不活性金属からなる
陽極4と陰極5が浸漬されている。
The treatment with the redox decontamination solution is carried out using a redox decontamination apparatus as shown in FIG. 3, for example. In FIG. 3, reference numeral 1 is an electrolytic tank, reference numeral 2 is a decontamination tank, and a decontaminating agent C is present in the electrolytic tank 1 and the decontamination tank 2.
An acidic redox decontamination solution 3 in which e 3+ and Ce 4+ are dissolved is stored. Further, an anode 4 and a cathode 5 made of an inert metal are immersed in the electrolytic cell 1.

【0005】放射能で汚染された金属廃棄物6は除染槽
2内の除染液3に浸漬され、金属廃棄物6をMとする以
下の溶解反応により金属廃棄物6から放射能が除去され
る。
The metal waste 6 contaminated with radioactivity is immersed in the decontamination solution 3 in the decontamination tank 2, and the radioactivity is removed from the metal waste 6 by the following dissolution reaction in which the metal waste 6 is M. To be done.

【0006】 Ce4++M→Ce3++M+ (1) この除染槽2と電解槽1とは循環配管7とオーバーフロ
ー配管8によって接続されており、循環ポンプ9により
除染液3は、電解槽1と除染槽2を循環する。
Ce 4+ + M → Ce 3+ + M + (1) The decontamination tank 2 and the electrolytic cell 1 are connected by a circulation pipe 7 and an overflow pipe 8, and the decontamination liquid 3 is collected by a circulation pump 9. The electrolytic bath 1 and the decontamination bath 2 are circulated.

【0007】このため、金属廃棄物6の溶解により消費
されたCe4+は、電解槽2において陽極4と陰極5の間
に直流電圧が印加されているため、以下の反応を生起し
て陽極で再生される。
For this reason, the Ce 4+ consumed by the dissolution of the metal waste 6 causes the following reaction because the direct current voltage is applied between the anode 4 and the cathode 5 in the electrolytic cell 2. Will be played.

【0008】 Ce3+→Ce4++e (2) このようにして金属廃棄物を大量に除染すると、除染液
中の溶出金属(Fe、Cr、Ni等)イオン濃度が増加すると
ともに放射能(Co、Mn等)濃度が増加して、作業員の被
爆量が増えるため、除染液を除染廃液として廃棄しなけ
ればならない。
Ce 3+ → Ce 4+ + e (2) When a large amount of metal waste is decontaminated in this way, the concentration of the eluted metal (Fe, Cr, Ni, etc.) ions in the decontamination solution increases, and radiation is emitted. Since the concentration of Noh (Co, Mn, etc.) increases and the amount of workers exposed to radiation increases, the decontamination liquid must be discarded as decontamination waste liquid.

【0009】従来この除染廃液の廃棄処理は、溶出金属
イオンおよび酸化力を有するCe4+を含む除染廃液をそ
のままドラム缶に入れて貯蔵するとドラム缶を腐食して
しまうので、還元剤を添加して還元し、これを廃液処理
施設に移送して中和処理したのち乾燥・固化する方法が
とられていた。
[0009] Conventionally, in the disposal treatment of this decontamination waste liquid, if the decontamination waste liquid containing elution metal ions and Ce 4+ having an oxidizing power is directly stored in the drum can and the drum can is corroded, a reducing agent is added. It has been used to reduce and reduce it, transfer it to a waste liquid treatment facility, neutralize it, and then dry and solidify it.

【0010】[0010]

【発明が解決しようとする課題】しかしながら、上述し
た除染廃液の処理方法は次のような課題を有していた。
However, the above-mentioned method for treating the decontamination waste liquid has the following problems.

【0011】(1)除染廃液を全て廃棄処分にすると、
放射性の二次廃棄物の発生量が大きい。
(1) When all the decontamination waste liquid is discarded,
A large amount of radioactive secondary waste is generated.

【0012】(2)除染廃液を廃棄処理する際、還元剤
および中和剤を添加して溶出金属イオンを水酸化物に置
換し、乾燥して固化するため、放射性の二次廃棄物の量
が増加する。
(2) When the decontamination waste liquid is disposed of, a reducing agent and a neutralizing agent are added to replace the eluted metal ions with hydroxides, and the solids are dried and solidified. The amount increases.

【0013】(3)Ce4+が完全に還元されない場合、
廃液処理施設に腐食を及ぼす。
(3) When Ce 4+ is not completely reduced,
Corrosion of waste liquid treatment facility.

【0014】本発明は、上記した課題を解決するために
なされたもので、放射性の金属イオン(例えばCo、M
n等)と金属廃棄物から溶出した金属イオン(例えば鉄
イオン、ニッケルイオン、クロムイオン等)が溶解して
いる除染廃液の処理に際し、除染液として再使用するこ
とができ、さらに廃液処理に伴う放射性の二次廃棄物の
発生量を低減することができる除染廃液の処理方法を提
供することを目的とする。
The present invention has been made in order to solve the above-mentioned problems, and has radioactive metal ions (for example, Co and M).
n)) and metal ions (eg, iron ions, nickel ions, chromium ions) eluted from the metal waste are dissolved, it can be reused as a decontamination liquid and can be further treated as waste liquid. It is an object of the present invention to provide a method for treating decontamination waste liquid, which can reduce the amount of radioactive secondary waste generated due to the above.

【0015】[0015]

【課題を解決するための手段】すなわち本発明は、放射
性物質で汚染された金属廃棄物をCe含有の酸性除染液
を用いて除染することによって発生する放射性除染廃液
の処理方法において、この除染廃液を電解酸化処理し廃
液中の3価のCeを4価のCeに酸化する電解酸化処理
工程と、電解酸化処理した除染廃液から錯陰イオンとし
て存在する4価のCeと酸を陰イオン交換膜を介して分
離する拡散透析工程と、この拡散透析工程で分離した酸
とCeを除染液として再使用するために濃度調整を行う
濃度調整工程と、拡散透析工程後のCeと酸を分離除去
した処理廃液を還元処理し化学的に安定化する還元処理
工程と、還元処理した処理廃液を中和する中和処理工程
と、中和処理した処理廃液を保管するために乾燥・固化
する乾燥・固化工程とからなることを特徴とする。
Means for Solving the Problems That is, the present invention relates to a method for treating a radioactive decontamination waste liquid generated by decontaminating a metal waste contaminated with a radioactive substance using an acidic decontamination liquid containing Ce, An electrolytic oxidation treatment step of electrolytically oxidizing the decontamination waste liquid to oxidize trivalent Ce in the waste liquid to tetravalent Ce, and tetravalent Ce and acid existing as complex anions from the electrolytic deoxidization-treated decontamination waste liquid Diffusion dialysis step for separating the acid and Ce through an anion exchange membrane, a concentration adjustment step for adjusting the concentration of the acid and Ce separated in the diffusion dialysis step for reuse as a decontamination solution, and a Ce after the diffusion dialysis step. A reduction treatment step to reduce and chemically stabilize the treated waste liquid from which the acid and acid have been separated and removed, a neutralization treatment step to neutralize the reduced treatment waste liquid, and a drying process to store the neutralized treated waste liquid.・ Drying / solidifying to solidify Characterized by comprising the a.

【0016】[0016]

【作用】上記の構成を有する除染廃液の処理方法におい
て、電解酸化処理工程で除染廃液中のCe3+をCe4+
酸化する。これは、除染剤であるCe3+、Ce4+のうち
Ce4+は酸性溶液中で陰イオン交換膜を通過する錯陰イ
オンを形成するため、拡散透析工程に先立ってCe4+
回収率を向上させるために行われる。拡散透析工程では
電解酸化処理後の廃液を陰イオン交換膜を介して透析水
と対向流に通液する。この通液中に、透析水との濃度差
により除染廃液中の酸と錯陰イオンを形成するCe4+
陰イオン交換膜を通過して透析水側に移動する。このた
め、除染廃液から酸とCe4+を容易に回収することがで
きる。陰イオン交換膜を用いた拡散透析処理による酸の
回収は、各種メッキ廃液からの酸の回収等、一般の化学
工業で利用されているが、本発明では、除染廃液中の酸
とともに、除染剤であるCeをも回収し、除染液として
再利用できるようにしたものである。
In the method for treating decontamination waste liquid having the above structure, Ce 3+ in the decontamination waste liquid is oxidized to Ce 4+ in the electrolytic oxidation treatment step. This is decontaminant Ce 3+, since Ce 4+ of Ce 4+ is to form a complex anions passing through the anion exchange membrane in an acidic solution, the Ce 4+ prior to the diffusion dialysis step This is done to improve the recovery rate. In the diffusion dialysis step, the waste liquid after the electrolytic oxidation treatment is passed through the anion exchange membrane in a counter flow with dialyzed water. During this passage, Ce 4+, which forms a complex anion with the acid in the decontamination waste liquid due to the difference in concentration with the dialysis water, moves to the dialysis water side through the anion exchange membrane. Therefore, the acid and Ce 4+ can be easily recovered from the decontamination waste liquid. Acid recovery by diffusion dialysis treatment using an anion exchange membrane is used in general chemical industry such as recovery of acid from various plating waste liquids, but in the present invention, it is removed along with the acid in the decontamination waste liquid. Ce, which is a dyeing agent, is also collected so that it can be reused as a decontamination solution.

【0017】拡散透析工程で分離回収した酸とCe
4+は、濃度調整工程で所定の濃度に調整され、除染液と
して再使用される。一方、Ce4+と酸を分離除去した後
の廃液は、除染剤である酸とCe4+が若干残留するた
め、還元処理工程で化学的に安定化し、ついで中和−乾
燥−固化して放射性廃棄物として保管する。
Acid and Ce separated and recovered in the diffusion dialysis step
4+ is adjusted to a predetermined concentration in the concentration adjustment process and reused as a decontamination solution. On the other hand, the waste liquid after the Ce 4+ and the acid have been separated and removed contains a slight amount of the decontaminating agent acid and Ce 4+, so it is chemically stabilized in the reduction treatment step, and then neutralized-dried-solidified. And store as radioactive waste.

【0018】したがって、この処理方法によれば、除染
廃液中の有効成分を分離回収して再利用することができ
るとともに、放射性廃棄物の発生量を低減することがで
きる。
Therefore, according to this treatment method, the active ingredient in the decontamination waste liquid can be separated and recovered and reused, and the amount of radioactive waste generated can be reduced.

【0019】[0019]

【実施例】以下、図面に基づいて本発明の実施例をレド
ックス除染廃液を例にして説明する。図1は本発明の除
染廃液の処理方法の一実施例を示すブロックフローチャ
ートである。この図に示すように、廃棄処理手順として
は除染廃液11を電解酸化処理工程12で電解し、前記
(2)式に示した酸化反応により除染廃液中のCe4+
度を上げる。なお、電解酸化処理は、前述の図3に示し
た電解槽2で行う。
Embodiments of the present invention will be described below with reference to the drawings, using a redox decontamination waste liquid as an example. FIG. 1 is a block flow chart showing an embodiment of the method for treating decontamination waste liquid according to the present invention. As shown in this figure, as the disposal procedure, the decontamination waste liquid 11 is electrolyzed in the electrolytic oxidation treatment step 12, and the Ce 4+ concentration in the decontamination waste liquid is increased by the oxidation reaction shown in the formula (2). The electrolytic oxidation treatment is performed in the electrolytic cell 2 shown in FIG.

【0020】この電解酸化処理工程12で酸化処理した
後に、拡散透析工程13で除染廃液11と透析水14を
陰イオン交換膜15を介して互いに反対側から通水する
と、除染廃液11中の酸および錯陰イオンを形成したC
4+は陰イオン交換膜15を通過して透析水へ移動し、
回収溶液16として回収される。この回収溶液16は濃
度調整工程17でCe4+とCe3+濃度および酸濃度の調
整が行われた後、除染液として再使用18される。
After the oxidation treatment in the electrolytic oxidation treatment step 12, when the decontamination waste liquid 11 and the dialysate water 14 are passed from the opposite sides through the anion exchange membrane 15 in the diffusion dialysis step 13, the decontamination waste liquid 11 contains Acid and C forming complex anions
e 4+ passes through the anion exchange membrane 15 and moves to dialysis water,
It is recovered as the recovery solution 16. The recovered solution 16 is reused as a decontamination solution after the Ce 4+ , Ce 3+ concentration and the acid concentration are adjusted in the concentration adjusting step 17.

【0021】拡散透析工程13における拡散透析原理を
図2に示す。透析操作としては、陰イオン交換膜15に
よって垂直に隔離された透析装置13aの片側室Aの下
部から酸化処理廃液11aを流入させ、透析水14を他
方側室Bの上部から入れて下降流で流す。酸化処理廃液
11a中の酸およびCe4+は、透析水14側へ拡散しな
がら上部に行くほど濃度が低下する。透析水14は拡散
してきた酸およびCe4+によって次第に酸およびCe4+
濃度が濃くなって下部に至る。このように、陰イオン交
換膜15を介して対向流で流すことにより、両室A、B
側とも垂直方向に上部ほど比重が小さく、下部ほど比重
が大きい安定した比重勾配層が形成されるため、陰イオ
ン交換膜15を介して接する酸化処理廃液11aと透析
水14の各部の酸およびCe4+の濃度差は、ほぼ一定と
なる。したがって、酸化処理廃液11a中の酸およびC
4+は透析水14側へほぼ全量移行し、回収溶液16と
して回収される。
The principle of diffusion dialysis in the diffusion dialysis step 13 is shown in FIG. As the dialysis operation, the oxidation treatment waste liquid 11a is introduced from the lower part of the one side chamber A of the dialysis device 13a which is vertically isolated by the anion exchange membrane 15, and the dialysis water 14 is introduced from the upper part of the other side chamber B to flow in a downward flow. .. The concentration of the acid and Ce 4+ in the oxidation treatment waste liquid 11a is lowered toward the upper part while diffusing to the dialyzed water 14 side. The dialysis water 14 is gradually converted into acid and Ce 4+ by the diffused acid and Ce 4+.
The concentration increases and reaches the bottom. In this way, by flowing in a counter flow through the anion exchange membrane 15, both chambers A, B
In both sides, a stable specific gravity gradient layer is formed in which the upper part has a smaller specific gravity in the vertical direction and the lower part has a larger specific gravity. Therefore, acid and Ce in each part of the oxidation treatment waste liquid 11a and the dialyzed water 14 contacting each other through the anion exchange membrane 15 The 4+ concentration difference is almost constant. Therefore, the acid and C in the oxidation treatment waste liquid 11a are
Almost the entire amount of e 4+ is transferred to the dialyzed water 14 side and is recovered as a recovery solution 16.

【0022】一方、酸化処理廃液11aは透析装置13
aの上部出口おいて透析水14との酸濃度差が小さく保
たれるため、ほとんど酸およびCe4+の除去された処理
廃液19として回収される。
On the other hand, the oxidation treatment waste liquid 11a is used as a dialysis device 13
Since the difference in acid concentration with the dialyzed water 14 is kept small at the upper outlet of a, it is recovered as the treatment waste liquid 19 from which most of the acid and Ce 4+ have been removed.

【0023】この処理廃液19中には若干のCe4+が残
留するため、図1に示すように、還元処理工程20で過
酸化水素を添加して化学的に安定なCe3+に還元する。
還元処理した後の処理廃液は、中和処理工程21で水酸
化ナトリウム水溶液により中和し、乾燥・固化工程22
で中和処理により発生したスラッジおよびNa塩を乾燥
・固化して放射性廃棄物として保管する。
Since a small amount of Ce 4+ remains in this treatment waste liquid 19, hydrogen peroxide is added in the reduction treatment step 20 to reduce it to chemically stable Ce 3+ , as shown in FIG. ..
The treated waste liquid after the reduction treatment is neutralized with a sodium hydroxide aqueous solution in the neutralization treatment step 21, and then dried / solidified step 22.
The sludge and Na salt generated by the neutralization process in 1. are dried and solidified and stored as radioactive waste.

【0024】次に、具体的な実施例をあげて、本発明に
係る除染廃液の処理方法にしたがって処理した場合の廃
棄物発生量を算出し、従来例との比較を行う。
Next, the concrete examples will be given to calculate the amount of waste generated when treated according to the method for treating decontamination waste liquid according to the present invention, and to compare with the conventional example.

【0025】第1の実施例として、硝酸系レドックス除
染廃液を選択し、この除染廃液を1000リットル処理
した場合の廃棄物発生量を求める。硝酸系レドックス廃
液中には除染剤である硝酸、Ce4+、Ce3+の他に溶出
金属としてFeが溶解しており、Ce4+は錯陰イオン
[Ce(NO3 6 2-として存在している。除染廃液
のそれぞれの成分濃度は硝酸が2mol/l 、Ce(Ce4+
+Ce3+)が0.8mol/l 、Feが1mol/l とする。
As a first example, a nitric acid redox decontamination waste liquid is selected, and the amount of waste generated when 1000 liters of this decontamination waste liquid is treated is determined. In the nitric acid-based redox waste liquid, in addition to nitric acid, Ce 4+ and Ce 3+ which are decontaminating agents, Fe is dissolved as an elution metal, and Ce 4+ is a complex anion [Ce (NO 3 ) 6 ] 2 -Exists as. The concentration of each component in the decontamination waste liquid was 2 mol / l of nitric acid, Ce (Ce 4+
+ Ce 3+ ) is 0.8 mol / l and Fe is 1 mol / l.

【0026】この除染廃液を電解酸化処理すると、除染
廃液中のCe4+/Ce濃度比は0.85まで上昇し、つ
いでこれを拡散透析処理することによって、Ce4+の8
0%、硝酸の80%が回収される。拡散透析処理した処
理廃液は、過酸化水素を添加して処理廃液中に残留する
Ce4+を化学的に安定なCe3+に還元した後、中和−蒸
発−乾燥処理する。この処理によって、以下に示す水酸
化物およびNa塩が廃棄物として発生する。
When this decontamination waste liquid is subjected to electrolytic oxidation treatment, the Ce 4+ / Ce concentration ratio in the decontamination waste liquid rises to 0.85, and then this is subjected to diffusion dialysis treatment to obtain Ce 4+ of 8%.
0% and 80% of nitric acid are recovered. The treated waste liquid subjected to the diffusion dialysis treatment is subjected to neutralization-evaporation-drying treatment after hydrogen peroxide is added to reduce Ce 4+ remaining in the treated waste liquid to chemically stable Ce 3+ . By this treatment, the hydroxide and Na salt shown below are generated as waste.

【0027】 Ce(OH)3 =(1-0.85×0.8)×0.8 mol/l ×1000 l×191 g/
mol=48.9kg Fe(OH)3 =1 mol/l×1000 l×107 g/mol=107kg NaNO3 =[{(1-0.85×0.8)×0.8 mol/l+1 mol/l}×3+2
mol/l ×0.2]×1000 l×85 g/mol=354kg 合計 =510kg 次に、上記硝酸系レドックス除染廃液を従来の処理方法
に従って廃棄する場合の廃棄物発生量を求める。従来例
では除染廃液中のCe4+を過酸化水素を添加して化学的
に安定なCe3+に還元し、中和−蒸発−乾燥処理する。
この処理によって、以下に示す水酸化物およびNa塩が
廃棄物として発生する。
Ce (OH) 3 = (1-0.85 × 0.8) × 0.8 mol / l × 1000 l × 191 g /
mol = 48.9kg Fe (OH) 3 = 1 mol / l × 1000 l × 107 g / mol = 107kg NaNO 3 = [{(1-0.85 × 0.8) × 0.8 mol / l + 1 mol / l} × 3 + 2
mol / l × 0.2] × 1000 l × 85 g / mol = 354 kg Total = 510 kg Next, calculate the amount of waste generated when the nitric acid redox decontamination waste liquid is discarded according to the conventional treatment method. In the conventional example, Ce 4+ in the decontamination waste liquid is reduced to chemically stable Ce 3+ by adding hydrogen peroxide, and neutralization-evaporation-drying treatment is performed.
By this treatment, the hydroxide and Na salt shown below are generated as waste.

【0028】 Ce(OH)3 =0.8 mol/l×1000 l×191 g/mol=153kg Fe(OH)3 =1 mol/l×1000 l×107 g/mol=107kg NaNO3 ={(0.8 mol/l+1 mol/l) ×3+2 mol/l}×1000 l
×85 g/mol=629kg 合計 =889kg 表1に第1の実施例と従来例の除染廃液を廃棄する場合
の廃液の処理方法に伴う廃棄物発生量を検討した結果を
比較して示す。
Ce (OH) 3 = 0.8 mol / l × 1000 l × 191 g / mol = 153 kg Fe (OH) 3 = 1 mol / l × 1000 l × 107 g / mol = 107 kg NaNO 3 = {(0.8 mol / l + 1 mol / l) × 3 + 2 mol / l} × 1000 l
× 85 g / mol = 629 kg Total = 889 kg Table 1 shows a comparison of the results of examining the amount of waste generated according to the waste liquid treatment method when discarding the decontamination waste liquid of the first example and the conventional example.

【0029】[0029]

【表1】 表1から明らかなように、除染廃液1000リットルを
廃棄処理した場合の廃棄物発生量は、本発明に係る第1
の実施例の場合は510kg、従来例の除染廃液を処理
せずにそのまま廃棄する場合は889kgとなることが
認められた。
[Table 1] As is clear from Table 1, the amount of waste generated when 1000 liters of decontamination waste liquid is disposed of is the first amount according to the present invention.
In the case of the above example, it was confirmed to be 510 kg, and in the case of discarding the decontamination waste liquid of the conventional example as it is without processing, it was recognized to be 889 kg.

【0030】以上説明したように、第1の実施例によれ
ば、Ce、硝酸、Feが溶解した硝酸系レドックス除染
廃液を陰イオン交換膜を用いた拡散透析によりCe、硝
酸を回収するため、従来の廃液処理方法に比べ廃棄物の
発生量を少なくすることができるとともに、回収したC
e、硝酸は硝酸系レドックス除染として再使用すること
ができる。
As described above, according to the first embodiment, in order to recover Ce and nitric acid, the nitric acid redox decontamination waste liquid in which Ce, nitric acid and Fe are dissolved is subjected to diffusion dialysis using an anion exchange membrane. The amount of waste generated can be reduced compared to the conventional waste liquid treatment method, and the recovered C
e, nitric acid can be reused for nitric acid redox decontamination.

【0031】なお、上記実施例では硝酸濃度2mol/l 、
Ce(Ce4++Ce3+)濃度0.8mol/l 、Fe濃度1
mol/l の硝酸系レドックス除染廃液を処理する場合につ
いて説明したが、それぞれ硝酸濃度0.01〜10mol/
l 、Ce(Ce4++Ce3+)濃度0.01〜2mol/l 、
Fe濃度0.01〜2mol/l の除染廃液でも同様にして
処理することができる。また溶出金属としてCr、Ni
が溶解しても本発明の処理方法を適用することができ
る。
In the above embodiment, the nitric acid concentration is 2 mol / l,
Ce (Ce 4+ + Ce 3+ ) concentration 0.8 mol / l, Fe concentration 1
The case of treating mol / l nitric acid redox decontamination waste liquid was explained, but the nitric acid concentration was 0.01 to 10 mol / l, respectively.
l, Ce (Ce 4+ + Ce 3+ ) concentration 0.01 to 2 mol / l,
A decontamination waste liquid having an Fe concentration of 0.01 to 2 mol / l can be treated in the same manner. In addition, as elution metals,
Even if is dissolved, the treatment method of the present invention can be applied.

【0032】次に、第2の実施例として硫酸系レドック
ス除染廃液を選択し、除染廃液を1000リットル処理
した場合について説明する。硫酸系レドックス廃液中に
は除染剤である硫酸、Ce4+、Ce3+の他に溶出金属と
してFeが溶解しており、Ce4+は[Ce(S
4 4 4-として存在している。除染廃液のそれぞれ
の成分濃度は硫酸が1mol/l 、Ce(Ce4++Ce3+
が0.2mol/l 、Feが1mol/l とする。
Next, as a second embodiment, a case where a sulfuric acid redox decontamination waste liquid is selected and 1000 liters of the decontamination waste liquid is treated will be described. In the sulfuric acid redox waste liquid, Fe is dissolved as a metal to be eluted in addition to sulfuric acid, Ce 4+ and Ce 3+ which are decontaminating agents, and Ce 4+ is [Ce (S
O 4 ) 4 ] 4− exists. Concentration of each component of decontamination waste liquid is 1 mol / l of sulfuric acid, Ce (Ce 4+ + Ce 3+ )
Is 0.2 mol / l and Fe is 1 mol / l.

【0033】この除染廃液を電解酸化処理することによ
って、除染廃液中のCe4+/Ce濃度比を0.85まで
上げ、ついでこれを拡散透析処理することによって、C
4+を80%、硫酸を80%回収する。拡散透析処理し
た処理廃液は、過酸化水素を添加して処理廃液中に残留
するCe4+を化学的に安定なCe3+に還元した後、中和
−蒸発−乾燥処理する。この結果、以下に示す水酸化物
およびNa塩が廃棄物として発生する。
By subjecting this decontamination waste liquid to electrolytic oxidation treatment, the Ce 4+ / Ce concentration ratio in the decontamination waste liquid is raised to 0.85, and then this is subjected to diffusion dialysis treatment to obtain C
Recover 80% of e 4+ and 80% of sulfuric acid. The treated waste liquid subjected to the diffusion dialysis treatment is subjected to neutralization-evaporation-drying treatment after hydrogen peroxide is added to reduce Ce 4+ remaining in the treated waste liquid to chemically stable Ce 3+ . As a result, the hydroxides and Na salts shown below are generated as waste.

【0034】 Ce(OH)3 =(1-0.85×0.8)×0.2 mol/l ×1000 l×191 g/
mol=12.2kg Fe(OH)3 =1 mol/l×1000 l×107 g/mol=107kg Na2 SO4 =[{(1-0.85×0.8)×0.2 mol/l+1 mol/l}×1.5+
1 mol/l ×0.2]×1000 l×142 g/mol=255kg 合計 =374kg 次に、上記硫酸系レドックス除染廃液を従来の処理方法
に従って廃棄する場合の廃棄物発生量を求める。除染廃
液中のCe4+を過酸化水素を添加して化学的に安定なC
3+に還元し、中和−蒸発−乾燥処理する。この処理に
よって、水酸化物およびNa塩が廃棄物として発生す
る。
Ce (OH) 3 = (1-0.85 × 0.8) × 0.2 mol / l × 1000 l × 191 g /
mol = 12.2kg Fe (OH) 3 = 1 mol / l × 1000 l × 107 g / mol = 107kg Na 2 SO 4 = [{(1-0.85 × 0.8) × 0.2 mol / l + 1 mol / l} × 1.5+
1 mol / l × 0.2] × 1000 l × 142 g / mol = 255 kg Total = 374 kg Next, calculate the amount of waste generated when the above sulfuric acid redox decontamination waste liquid is discarded according to the conventional treatment method. Ce 4+ in decontamination waste liquid is chemically stable by adding hydrogen peroxide.
It is reduced to e 3+ and neutralized-evaporated-dried. This treatment produces hydroxides and Na salts as waste.

【0035】 Ce(OH)3 =0.2 mol/l×1000 l×191 g/mol=38.2kg Fe(OH)3 =1 mol/l×1000 l×107g/mol=107kg Na2 SO4 ={(0.2 mol/l+1 mol/l) ×1.5+1 mol/l}×1000
l×142g/mol=398kg 合計 =543kg 表2に第2の実施例と従来例の除染廃液を廃棄する場合
の廃液の処理方法に伴う廃棄物発生量を検討した結果を
比較して示す。
Ce (OH) 3 = 0.2 mol / l × 1000 l × 191 g / mol = 38.2 kg Fe (OH) 3 = 1 mol / l × 1000 l × 107 g / mol = 107 kg Na 2 SO 4 = {( 0.2 mol / l + 1 mol / l) × 1.5 + 1 mol / l} × 1000
l × 142 g / mol = 398 kg Total = 543 kg Table 2 shows a comparison of the results of examining the amount of waste generated according to the waste liquid treatment method when discarding the decontamination waste liquids of the second example and the conventional example.

【0036】[0036]

【表2】 表2から明らかなように、除染廃液1000リットルを
廃棄処理した場合の廃棄物発生量は、本発明に係る第2
の実施例の場合は374kg、従来例の除染廃液を処理
せずにそのまま廃棄する場合は543kgとなること認
められた。
[Table 2] As is clear from Table 2, the amount of waste generated when 1000 liters of decontamination waste liquid is disposed of is the second amount according to the present invention.
It was confirmed that in the case of the above example, 374 kg was obtained, and when the decontamination waste liquid of the conventional example was discarded as it was without treatment, it was 543 kg.

【0037】以上説明したように、第2の実施例ではC
e、硫酸、Feが溶解した硫酸系レドックス除染廃液を
陰イオン交換膜を用いた拡散透析処理によりCe、硫酸
を回収することができるため、従来の廃液処理方法に比
べ廃棄物の発生量を少なくすることができる。また、回
収したCe、硫酸は、硫酸系レドックス除染液として再
使用することができる。
As described above, in the second embodiment, C
e, sulfuric acid, Fe dissolved sulfuric acid redox decontamination waste liquid by diffusion dialysis treatment using an anion exchange membrane, it is possible to recover Ce, sulfuric acid, compared to the conventional waste liquid treatment method, the amount of waste generated Can be reduced. The recovered Ce and sulfuric acid can be reused as a sulfuric acid redox decontamination solution.

【0038】なお、上記実施例においては硫酸系レドッ
クス除染廃液中の成分濃度を硫酸1mol/l 、Ce(Ce
4++Ce)1mol/l 、Fe1mol/l としたが、硫酸濃度
0.01〜0.5mol/l 、Ce濃度0.01〜5mol/l
、Fe濃度0.01〜2mol/l の硫酸系レドックス除
染廃液でも使用可能である。また溶出金属としてCr、
Niが溶解しても使用可能である。
In the above embodiment, the concentration of the components in the sulfuric acid redox decontamination waste liquid was 1 mol / l of sulfuric acid and Ce (Ce
4+ + Ce) 1 mol / l, Fe 1 mol / l, sulfuric acid concentration 0.01-0.5 mol / l, Ce concentration 0.01-5 mol / l
, A sulfuric acid redox decontamination waste liquid having an Fe concentration of 0.01 to 2 mol / l can also be used. In addition, as elution metal Cr,
It can be used even if Ni is dissolved.

【0039】[0039]

【発明の効果】以上説明したように、本発明によれば、
以下の効果がある。
As described above, according to the present invention,
It has the following effects.

【0040】(1)レドックス除染廃液から酸(硝酸ま
たは硫酸)、Ceを拡散透析により分離・回収し再使用
することができるため、除染廃液の発生量を少なくする
ことができる。
(1) Since the acid (nitric acid or sulfuric acid) and Ce can be separated and recovered by diffusion dialysis from the redox decontamination waste liquid and reused, the amount of the decontamination waste liquid generated can be reduced.

【0041】(2)また、従来の除染廃液をそのまま中
和処理して蒸発、乾燥、固化する方法と比較し、二次廃
棄物の発生量を低減することができる。
(2) In addition, the amount of secondary waste generated can be reduced as compared with the conventional method in which the decontamination waste liquid is neutralized as it is and then evaporated, dried and solidified.

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

【図1】本発明に係る除染廃液処理方法を示すブロック
フローチャートである。
FIG. 1 is a block flowchart showing a decontamination waste liquid treatment method according to the present invention.

【図2】拡散透析処理工程の原理を示す断面図である。FIG. 2 is a cross-sectional view showing the principle of a diffusion dialysis treatment process.

【図3】レドックス除染装置の一例を概略的に示す断面
図である。
FIG. 3 is a sectional view schematically showing an example of a redox decontamination device.

【符号の説明】[Explanation of symbols]

11………除染廃液 11a……酸化処理廃液 12………電解酸化処理工程 13………拡散透析工程 13a……透析装置 14………透析水 15………陰イオン交換膜 16………回収溶液 17………濃度調整工程 18………再使用 19………処理廃液 20………還元処理工程 21………中和処理工程 22………乾燥・固化工程 11 ………… Decontamination waste liquid 11a …… Oxidation treatment waste liquid 12 ………… Electrolytic oxidation treatment process 13 ………… Diffusion dialysis process 13a …… Dialyzer 14 ………… Dialysis water 15 ………… Anion exchange membrane 16 …… … Recovered solution 17 ………… Concentration adjustment process 18 ………… Reuse 19 ………… Treatment waste liquid 20 ………… Reduction treatment process 21 ………… Neutralization treatment process 22 ………… Drying / solidification process

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 放射性物質で汚染された金属廃棄物をC
e含有の酸性除染液を用いて除染することによって発生
する放射性除染廃液の処理方法において、 前記除染廃液を電解酸化処理し廃液中の3価のCeを4
価のCeに酸化する電解酸化処理工程と、 電解酸化処理した除染廃液から錯陰イオンを形成する4
価のCeと酸を陰イオン交換膜を介して分離する拡散透
析工程と、 この拡散透析工程で分離した酸とCeを除染液として再
使用するために濃度調整を行う濃度調整工程と、 前記拡散透析工程後のCeと酸を分離除去した処理廃液
を還元処理し化学的に安定化する還元処理工程と、 還元処理した処理廃液を中和する中和処理工程と、 中和処理した処理廃液を保管するために乾燥・固化する
乾燥・固化工程とを有することを特徴とする除染廃液の
処理方法。
1. A metal waste contaminated with radioactive substances is treated as C
In a method of treating radioactive decontamination waste liquid generated by decontaminating using an acid-containing decontamination liquid containing e, the decontamination waste liquid is subjected to electrolytic oxidation treatment to remove trivalent Ce in the waste liquid to 4
Electrolytic oxidation process to oxidize valent Ce and forming complex anion from decontamination waste liquid subjected to electrolytic oxidation process 4
A diffusion dialysis step of separating a high-valent Ce and an acid through an anion exchange membrane, a concentration adjustment step of performing a concentration adjustment to reuse the acid and Ce separated in the diffusion dialysis step as a decontamination solution, A reduction treatment step of reducing and chemically stabilizing the treatment waste fluid after separation and removal of Ce and acid after the diffusion dialysis step, a neutralization treatment step of neutralizing the reduction treatment waste fluid, and a neutralized treatment waste fluid A method for treating decontamination waste liquid, comprising: a drying / solidifying step of drying / solidifying for storing.
JP12727992A 1992-05-20 1992-05-20 Processing method for decontamination waste liquid Withdrawn JPH05323095A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP12727992A JPH05323095A (en) 1992-05-20 1992-05-20 Processing method for decontamination waste liquid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP12727992A JPH05323095A (en) 1992-05-20 1992-05-20 Processing method for decontamination waste liquid

Publications (1)

Publication Number Publication Date
JPH05323095A true JPH05323095A (en) 1993-12-07

Family

ID=14956051

Family Applications (1)

Application Number Title Priority Date Filing Date
JP12727992A Withdrawn JPH05323095A (en) 1992-05-20 1992-05-20 Processing method for decontamination waste liquid

Country Status (1)

Country Link
JP (1) JPH05323095A (en)

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