JPS6151598A - Method of reducing radioactive waste - Google Patents

Method of reducing radioactive waste

Info

Publication number
JPS6151598A
JPS6151598A JP59173407A JP17340784A JPS6151598A JP S6151598 A JPS6151598 A JP S6151598A JP 59173407 A JP59173407 A JP 59173407A JP 17340784 A JP17340784 A JP 17340784A JP S6151598 A JPS6151598 A JP S6151598A
Authority
JP
Japan
Prior art keywords
regeneration
exchange resin
ion exchange
chemical solution
amount
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
JP59173407A
Other languages
Japanese (ja)
Inventor
幸雄 池田
毅 吉岡
修一 上野
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.)
Ebara Corp
Original Assignee
Ebara 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 Ebara Corp filed Critical Ebara Corp
Priority to JP59173407A priority Critical patent/JPS6151598A/en
Publication of JPS6151598A publication Critical patent/JPS6151598A/en
Pending legal-status Critical Current

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Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、放射性物質を含むイオン交換装置におけるイ
オン交換樹脂の再生方法に関するものである。
DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a method for regenerating an ion exchange resin in an ion exchange device containing radioactive substances.

〔従来技術〕[Prior art]

従来、例えば原子力発電所における復水浄化系、即ち復
水脱塩装置において鉱、海水洲洩対策及び出口水の純度
を確保するため、イオン交換樹脂中のイオン負荷が極く
低い時点でイオン交換樹脂の再生が行われておジ、従っ
てこの際発生する再生廃液中には通薬量の90%以上の
未反応薬剤(苛性ソーダ或いは硫酸)が残留する結果と
なっている。
Conventionally, for example, in a condensate purification system in a nuclear power plant, that is, a condensate desalination device, ion exchange was performed at a point when the ion load in the ion exchange resin was extremely low in order to prevent ore and seawater leakage and to ensure the purity of the outlet water. As the resin is being regenerated, unreacted chemicals (caustic soda or sulfuric acid) remain in the regenerated waste liquid that is generated at this time in an amount of 90% or more of the amount passed.

そして、この未反応薬剤を含むイオン交換樹脂の再生廃
液はそのま\廃棄物処理系統へ送られ、蒸発濃縮した後
最終的には硫酸ナトリウムとして通常ドラム缶内でアス
ファルト或いはセメント等により固型化されるが、これ
ら固化物は放射性を有しており、容易に廃棄処分するこ
とができないので、現時点では発電所内に蓄積される一
方となっており、これら放射性廃棄物の処分は環境問題
ともからんで重要な課題の−つとなっている。
The recycled waste liquid of the ion exchange resin containing unreacted chemicals is sent as is to the waste treatment system, where it is evaporated and concentrated and finally solidified as sodium sulfate in a drum with asphalt or cement. However, these solidified wastes are radioactive and cannot be easily disposed of, so they are currently accumulating inside power plants, and the disposal of these radioactive wastes is not an environmental issue. This is one of the important issues.

〔発明の(画成〕[definition of invention]

本発明は、放射性イオンを含む液体をイオン交換したイ
オン交換樹脂を再生する方法において、前半に通液する
約1/2量の薬液は前回のイオン交換樹脂f’) 半時
の後半に用いた薬液を使用踵後半に通液する約1/2量
め薬液は新しく調整した薬液を使用することを特徴とす
る、イオン交換樹脂再生時における放射性廃棄物の低減
方法である。
The present invention is a method for regenerating an ion exchange resin obtained by ion-exchanging a liquid containing radioactive ions, in which approximately 1/2 the amount of chemical solution passed in the first half of the previous ion exchange resin f') was used in the second half of half an hour. This method of reducing radioactive waste during ion exchange resin regeneration is characterized by using a newly prepared chemical solution for approximately 1/2 volume of the chemical solution passed through the back half of the heel.

木兄り]者等は、放射性廃棄物の処分方法は重大な社会
問題となっていることから、該処分方法を完全に解決し
えないまでも、処分すべき廃棄物を減少せしめる場合、
廃棄物の貯蔵容積を減少せしめうることから、イオン交
換樹脂再生時において排出される再生廃液?減少させる
方策について種々検討を行っているうちに本発明をなす
に到った。
Since the disposal method of radioactive waste has become a serious social issue, the people of Kienori and others believe that even if the disposal method cannot be completely solved, if the amount of waste to be disposed of is reduced,
Is the recycled waste liquid discharged during ion exchange resin regeneration because it can reduce the storage volume of waste? The present invention was developed while conducting various studies on ways to reduce this.

本発明は、イオン変換樹脂の再生に際し廃棄すべき再生
廃液中の未反応薬剤の量を減少せしめることにより、固
化物として蓄積される放射性廃棄物の量を減少せしめる
ものである。
The present invention reduces the amount of radioactive waste accumulated as a solidified product by reducing the amount of unreacted chemicals in the regeneration waste liquid that must be discarded during the regeneration of ion conversion resins.

原子力発電所等における通常の運転時のイオン負荷は、
脱塩塔1塔当v45000 fiθ/crrcm”で運
転されており、従ってイオン交換樹脂の再生時における
イオン交換樹脂のイオン負荷量も小さいものとせざるを
えないので、再生時における再生用薬剤溶液(通常8チ
のH2BO3及び4チのNaou )中の再生薬剤の消
*址は少なく、多量の未反応の薬剤即ち硫酸又は苛性ン
ーダが再生廃液中に存在している。
The ion load during normal operation at nuclear power plants, etc. is
The demineralization tower is operated at 45000 fiθ/crrcm per tower, and therefore the ion load on the ion exchange resin must be small during the regeneration of the ion exchange resin. Usually, the waste of the regeneration agent in 8 H2BO3 and 4 H Naou is small, and a large amount of unreacted agent, ie sulfuric acid or caustic powder, is present in the regeneration effluent.

通常のイオン交換樹脂再生の際における再生用薬剤溶液
中における薬剤量(通薬量)と再生廃液中に存在する未
反応薬剤量との関係を示すと次表のとおりである。
The following table shows the relationship between the amount of drug in the regeneration drug solution (drug passing amount) and the amount of unreacted drug present in the regeneration waste liquid during normal ion exchange resin regeneration.

再生廃液中には、上記表に示すとおり、多量の未反応の
再生剤を含有しているので、該再生廃液1&:繰り返し
使用することも考えられるが、再生廃液中Kに、N1i
あるいIrs、C4′等含まれており、イオン交換樹脂
の再生レベルが低下するだけでなく、繰り返し使用する
場合再生産液中の龍あるいはCt′が濃縮されるにつれ
、樹脂の再生レベルが異なったものとなり、脱塩操作上
も好ましくない。
As shown in the table above, the regenerated waste liquid contains a large amount of unreacted regenerant, so it is conceivable that the regenerated waste liquid 1&: may be used repeatedly, but the K in the regenerated waste liquid contains
In addition, the regeneration level of the ion exchange resin will not only decrease, but also the regeneration level of the resin will vary as the Irs or Ct' in the regeneration solution becomes concentrated when used repeatedly. This is not preferable in terms of desalting operations.

そこで、前記再生廃液で再生すべきイオン交換樹脂を処
理した後新しく調整した再生液で処理した所、比較的少
量の新しく調整した再生液を用いる場合、従来法におけ
るイオン交換樹脂の再生レベルと全く同様なレベルに再
生しうろことを見出だした。
Therefore, when the ion exchange resin to be regenerated was treated with the recycled waste liquid and then treated with the newly prepared regenerating liquid, when a relatively small amount of the newly prepared regenerating liquid was used, the regeneration level of the ion exchange resin was completely different from that in the conventional method. I found scales that regenerate to a similar level.

そして、イオン交換樹脂の再生レベルを一定の値に保持
しながら、且つ、連続的に再生を行うためには、再生の
前半に先づ前回のイオン交換樹脂の再生時の後半に用い
た゛全再生液の約1/2のj、、1:に相当する薬液を
使用して再生を行い、ついで全再生液の約1/2の量に
相当する新しく調整した薬液を使用して再生すると共に
、前半で使用した薬液のみを廃棄し、後半で使用した新
しく調整した薬液は次回の再生に利用するために貯留し
ておくことにより、イオン交換樹脂の再生レベルを従来
法と同様のレベルに保持しながら、廃棄する再生廃液の
f[tl−従来法の約1/2とすることができるもので
ある。
In order to maintain the regeneration level of the ion exchange resin at a constant value and perform continuous regeneration, the first half of the regeneration must be preceded by the "full regeneration" process used in the second half of the previous ion exchange resin regeneration. Regeneration is performed using a chemical solution corresponding to about 1/2 of the liquid, and then regeneration is performed using a newly prepared chemical solution corresponding to about 1/2 of the total regeneration solution. By discarding only the chemical solution used in the first half and storing the newly prepared chemical solution used in the second half for use in the next regeneration, the regeneration level of the ion exchange resin can be maintained at the same level as the conventional method. However, f[tl of the regenerated waste liquid to be discarded can be reduced to about 1/2 of that of the conventional method.

実施例 原子力発電所の復水脱塩装置のモデルプラントを用いて
イオン交換樹脂の再生処理実験を行った。
EXAMPLE An ion exchange resin regeneration treatment experiment was conducted using a model plant of a condensate desalination equipment at a nuclear power plant.

再生すべき混合イオン交換樹脂を先づ脱塩塔から陽イオ
ン交換樹脂再生塔に導き、常法に従って陰・陽画イオン
交換樹脂層に分離し、ついで陰イオン交換樹脂を陰イオ
ン交換樹脂再生塔に移送し、ついで両イオン交換樹脂を
夫々再生した。
The mixed ion exchange resin to be regenerated is first led from the demineralization tower to the cation exchange resin regeneration tower, separated into negative and positive ion exchange resin layers according to a conventional method, and then the anion exchange resin is led to the anion exchange resin regeneration tower. Both ion exchange resins were then regenerated, respectively.

先づ、陽イオン交換樹脂を逆況にょυ水洗した後前回の
陽イオン交換樹脂再生時の後半に用いた、全再生液の約
1/2の量に相当する量のH,So4再生液で処理し、
ついで後半を全再生液の約1/2の駄に相当する量の新
しく711整したH2So4再生液で処理した。この場
合、前半に使用した再生廃液は廃棄物処理ラインへ流し
、後半で使用した再生液は、次回の陽イオン交換樹脂再
生時の前半に使用するために貯留槽に貯留した。
First, after washing the cation exchange resin with water under reverse conditions, it was washed with H, So4 regenerating solution in an amount equivalent to about 1/2 of the total amount of regenerating solution used in the latter half of the previous cation exchange resin regeneration. process,
Then, the second half was treated with a freshly prepared H2So4 regenerating solution in an amount equivalent to about 1/2 of the total regenerating solution. In this case, the recycled waste liquid used in the first half was sent to the waste treatment line, and the recycled liquid used in the second half was stored in a storage tank for use in the first half of the next cation exchange resin regeneration.

陰イオン交換樹脂についても再生液として5裂のNaO
H水浴液を使用した以外は前記陽イオン交換樹脂の再生
と同様の方法で再生した。再生した両イオン交換樹脂は
常法に従って混合し、一時貯留した後脱塩塔に送り復水
の脱塩に供した。
For anion exchange resin, 5-fiber NaO is also used as a regenerating liquid.
It was regenerated in the same manner as the cation exchange resin regeneration described above except that H water bath solution was used. The regenerated both ion exchange resins were mixed according to a conventional method, temporarily stored, and then sent to a desalination tower for desalination of condensate.

上記方法によるイオン交換切崩の再生レベルは、全、吐
を新らしく調整した再生′tLを使用した場合と全く同
じであって、従来法による再生による場合と、再生方法
以外は全く同じ条件で運転を行ったが、復水の水質その
他従来法の場合と異なるところになかった。
The regeneration level of ion exchange cutting by the above method is exactly the same as when using regeneration 'tL with newly adjusted total and discharge, and under exactly the same conditions as regeneration using the conventional method except for the regeneration method. During the operation, there was no difference in the quality of the condensate or anything else compared to the conventional method.

〔発明の効果〕〔Effect of the invention〕

本発明は、イオン交換樹脂の再生に際し、後半に使用す
る全再生液の約1/2の量に相当する再生液の貯留槽並
びに核種への配管を設けることにより、再生レベルは従
来法と同様に保持しながら、再生廃液の量を従来法の約
1/2とすることが可能となり、従って再生廃液を固化
貯蔵する際の容積を1/2とすることが可能となる。
In the present invention, when regenerating the ion exchange resin, the regeneration level is the same as that of the conventional method by providing a storage tank for regeneration liquid equivalent to about 1/2 of the total amount of regeneration liquid used in the latter half and piping to the nuclide. It becomes possible to reduce the amount of regenerated waste liquid to about 1/2 of that of the conventional method while maintaining the regenerated waste liquid, and therefore, it becomes possible to reduce the volume when solidifying and storing the regenerated waste liquid to 1/2.

Claims (1)

【特許請求の範囲】 1、放射性イオンを含む液体をイオン交換したイオン交
換樹脂を再生する方法において、前半に通液する約1/
2量の薬液は前回のイオン交換樹脂再生時の後半に用い
た薬液を使用し、後半に通液する約1/2量の薬液は新
しく調整した薬液を使用することを特徴とする、イオン
交換樹脂再生時における放射性廃棄物の低減方法。 2、前半に通液した1/2量の薬液は廃棄し、後半に通
液した約1/2量の薬液は次回のイオン交換樹脂再生時
の前半に使用するために一時貯留する特許請求の範囲1
記載の放射性廃棄物の低減方法。
[Claims] 1. In a method for regenerating an ion-exchange resin obtained by ion-exchanging a liquid containing radioactive ions, about 1/2
An ion exchange method characterized by using the chemical solution used in the second half of the previous ion exchange resin regeneration for two amounts of the chemical solution, and using the newly prepared chemical solution for about half the amount of the chemical solution passed in the second half. Method for reducing radioactive waste during resin regeneration. 2. The 1/2 amount of the chemical solution passed in the first half is discarded, and the approximately 1/2 amount of the chemical solution passed in the second half is temporarily stored for use in the first half of the next ion exchange resin regeneration. range 1
Described radioactive waste reduction method.
JP59173407A 1984-08-22 1984-08-22 Method of reducing radioactive waste Pending JPS6151598A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59173407A JPS6151598A (en) 1984-08-22 1984-08-22 Method of reducing radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59173407A JPS6151598A (en) 1984-08-22 1984-08-22 Method of reducing radioactive waste

Publications (1)

Publication Number Publication Date
JPS6151598A true JPS6151598A (en) 1986-03-14

Family

ID=15959852

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59173407A Pending JPS6151598A (en) 1984-08-22 1984-08-22 Method of reducing radioactive waste

Country Status (1)

Country Link
JP (1) JPS6151598A (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS50128683A (en) * 1974-03-29 1975-10-09
JPS569379A (en) * 1979-07-03 1981-01-30 Tokyo Keiki Co Ltd Automatic anticorrosion equipment for cathode

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS50128683A (en) * 1974-03-29 1975-10-09
JPS569379A (en) * 1979-07-03 1981-01-30 Tokyo Keiki Co Ltd Automatic anticorrosion equipment for cathode

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