JPH0534497A - Process of radioactive waste liquid - Google Patents
Process of radioactive waste liquidInfo
- Publication number
- JPH0534497A JPH0534497A JP19521391A JP19521391A JPH0534497A JP H0534497 A JPH0534497 A JP H0534497A JP 19521391 A JP19521391 A JP 19521391A JP 19521391 A JP19521391 A JP 19521391A JP H0534497 A JPH0534497 A JP H0534497A
- Authority
- JP
- Japan
- Prior art keywords
- silicon
- oxygen
- waste liquid
- radioactive
- treating
- 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
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- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Abstract
Description
【産業上の利用分野】本発明は原子力発電所や原子燃料
再処理工場から発生する放射性廃液の処理方法に係り、
とくに、アルカリ廃液から放射性核種を吸着除去する方
法に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating radioactive waste liquid generated from a nuclear power plant or a nuclear fuel reprocessing plant,
In particular, it relates to a method for adsorbing and removing radionuclides from an alkaline waste liquid.
【従来の技術】原子力発電所や原子燃料再処理工場から
発生する放射性廃液からセシウム，ストロンチウム等の
放射性核種を除去するには、例えば、特開昭62−161097
号公報に記載されているようにキレート樹脂や合成ゼオ
ライトを用いた吸着処理が一般的である。これらの吸着
剤は処理液が中性の時、最も吸着性能が高いため、処理
液がアルカリ性の場合、吸着処理の前段で酸によるｐＨ
調整を実施する必要があった。2. Description of the Related Art To remove radioactive nuclides such as cesium and strontium from radioactive waste liquid generated from a nuclear power plant or a nuclear fuel reprocessing plant, see, for example, JP-A-62-161097.
As described in Japanese Patent Publication No. JP-A-2003-242, adsorption treatment using a chelate resin or synthetic zeolite is general. These adsorbents have the highest adsorption performance when the treatment liquid is neutral, so when the treatment liquid is alkaline, the pH due to the acid is added before the adsorption treatment.
Adjustments needed to be made.
【発明が解決しようとする課題】本発明は処理液がアル
カリ性の場合もｐＨ調整等の前処理操作が不要な吸着処
理を可能とする。The present invention enables an adsorption treatment which does not require a pretreatment operation such as pH adjustment even when the treatment liquid is alkaline.
【課題を解決するための手段】本発明では吸着剤とし
て、珪素と酸素で構成されるシロキサン結合と珪素と酸
素と水素で構成されるシラノール基を持つ珪素化合物、
もしくは、珪素と酸素とアルミニウムで構成されるアル
ミノシリケートを主成分とする無機物を使用し、本吸着
剤を充填した吸着装置にアルカリ廃液をそのまま通水
し、含有する放射性核種を吸着除去することを特徴とす
る。In the present invention, as an adsorbent, a silicon compound having a siloxane bond composed of silicon and oxygen and a silanol group composed of silicon, oxygen and hydrogen,
Alternatively, it is possible to use an inorganic substance composed mainly of aluminosilicate composed of silicon, oxygen and aluminum, and pass the alkaline waste liquid as it is through an adsorption device filled with this adsorbent to adsorb and remove the radionuclide contained in it. Characterize.
【作用】本吸着剤はアルカリ水溶液中で次の反応によ
り、シリカ主骨格の一部が分解し、陽イオン吸着性を持
つシラノール基を新たに生成する性質があることを発明
者等は基礎実験により見出した。[Function] The present inventors have conducted a basic experiment that the adsorbent has a property of partially decomposing a silica main skeleton by the following reaction in an alkaline aqueous solution to newly generate a silanol group having a cation adsorbing property. Found by.
【化１】
−Ｓi−Ｏ−Ｓi− ＋ ２ＮaＯＨ＝−Ｓi−ＯＮa ＮaＯ−Ｓi− ＋ Ｈ2Ｏ
従って、これらの吸着剤はアルカリ水溶液中で除去対象
である陽イオン核種の吸着容量が増大する特性を持って
いるため、アルカリ廃液からの核種除去の場合、ｐＨ調
整等の前処理の必要がなく、直接処理液と吸着剤を接触
すればよい。本発明の吸着剤には、酸性白土，クリスト
バライト，モンモリロナイト等の天然のシリカ化合物，
アルミノシリケート、及びクリノプチロライトを初めと
する天然のゼオライトが適する。## STR1 ## -Si-O-Si- + 2NaOH = -Si-ONa NaO-Si- + H 2 O Therefore, these adsorbents are increased adsorption capacity of the cation species is a removal target in an alkaline aqueous solution Because of its characteristics, when removing a nuclide from an alkali waste liquid, it is not necessary to perform pretreatment such as pH adjustment, and the treatment liquid and the adsorbent may be directly contacted with each other. The adsorbent of the present invention includes natural silica compounds such as acid clay, cristobalite and montmorillonite,
Natural zeolites such as aluminosilicates and clinoptilolite are suitable.
【実施例】本実施例は放射性セシウムを含む廃液（中
性、アルカリ性）を処理した結果について示す。実施方
法は廃液１ｌに吸着剤粉末を５０ｇ添加し、約一時間撹
拌した後、遠心分離で吸着剤と廃液を分離した。廃液中
の放射性セシウムの吸着処理前後の比を除染係数と定義
して、表１に示す。EXAMPLE This example shows the result of treating a waste liquid (neutral and alkaline) containing radioactive cesium. As an implementation method, 50 g of adsorbent powder was added to 1 liter of waste liquid, and after stirring for about 1 hour, the adsorbent and waste liquid were separated by centrifugation. Table 1 defines the ratio of radioactive cesium in the waste liquid before and after the adsorption treatment as the decontamination coefficient.
【表１】
表１のように本発明の吸着剤はアルカリ廃液でも十分に
高い除染係数を示し、吸着処理の前段のｐＨ調整操作が
不要であることが判った。本実施例は図１に示すような
吸着装置１に廃液を通水することによって実施すること
ができる。ここで、使用済みの吸着剤はセメントペース
トと混合し、固化容器内に安定に固形化され、最終処分
可能な固化体となる。[Table 1] As shown in Table 1, the adsorbent of the present invention showed a sufficiently high decontamination coefficient even with an alkaline waste liquid, and it was found that the pH adjusting operation before the adsorption treatment is unnecessary. This embodiment can be carried out by passing the waste liquid through the adsorption device 1 as shown in FIG. Here, the used adsorbent is mixed with the cement paste and is stably solidified in the solidification container to be a solidified body that can be finally disposed.
【発明の効果】本発明によれば、陽イオン核種を含むア
ルカリ性の放射性廃液から前処理操作なく高い除染係数
で核種を吸着除去することができる。According to the present invention, nuclides can be adsorbed and removed from an alkaline radioactive waste liquid containing a cation nuclide with a high decontamination coefficient without pretreatment.
【図１】本発明の一実施例の放射性廃液処理装置の系統
図。FIG. 1 is a system diagram of a radioactive liquid waste treatment apparatus according to an embodiment of the present invention.
１…吸着装置、２…廃液タンク、３…固化容器、４…セ
メント混練機。1 ... Adsorption device, 2 ... Waste liquid tank, 3 ... Solidification container, 4 ... Cement kneader.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 松田 将省 茨城県日立市森山町1168番地 株式会社日 立製作所エネルギー研究所内 (72)発明者 千野 耕一 茨城県日立市森山町1168番地 株式会社日 立製作所エネルギー研究所内 (72)発明者 池田 孝志 茨城県日立市森山町1168番地 株式会社日 立製作所エネルギー研究所内 ─────────────────────────────────────────────────── ─── Continued front page (72) Inventor Shouda Matsuda 1168 Moriyama-cho, Hitachi-shi, Ibaraki Japan Tate Seisakusho Energy Research Institute (72) Inventor Koichi Chino 1168 Moriyama-cho, Hitachi-shi, Ibaraki Japan Tate Seisakusho Energy Research Institute (72) Inventor Takashi Ikeda 1168 Moriyama-cho, Hitachi-shi, Ibaraki Japan Tate Seisakusho Energy Research Institute
Claims (6)
珪素と酸素と水素で構成されるシラノール基を持つ珪素
化合物を用いた放射性廃液の処理方法。1. A method for treating radioactive waste liquid using a silicon compound having a siloxane bond composed of silicon and oxygen and a silanol group composed of silicon, oxygen and hydrogen.
ルミノシリケートを主成分とする無機物を用いた放射性
廃液の処理方法。2. A method for treating a radioactive waste liquid using an inorganic material whose main component is aluminosilicate composed of silicon, oxygen and aluminum.
珪素と酸素と水素で構成されるシラノール基を持つ珪素
化合物を充填した吸着装置を用いた吸着処理を特徴とす
る放射性廃液の処理方法。3. A method for treating radioactive waste liquid, which comprises an adsorption treatment using an adsorption device filled with a silicon compound having a siloxane bond composed of silicon and oxygen and a silanol group composed of silicon, oxygen and hydrogen.
ルミノシリケートを主成分とする無機物を充填した吸着
装置を用いた吸着処理を特徴とする放射性廃液の処理方
法。4. A method for treating a radioactive waste liquid, which is characterized by an adsorption treatment using an adsorption device filled with an inorganic substance whose main component is aluminosilicate composed of silicon, oxygen and aluminum.
珪素と酸素と水素で構成されるシラノール基を持つ珪素
化合物を充填した吸着装置にアルカリ廃液をそのまま通
水し、含有する放射性核種を吸着除去することを特徴と
する放射性廃液の処理方法。5. An alkali waste liquid is passed as it is to an adsorption device filled with a silicon compound having a silanol group composed of silicon, oxygen and hydrogen and a siloxane bond composed of silicon and oxygen, and adsorbs a radionuclide contained therein. A method for treating a radioactive liquid waste, which comprises removing the radioactive liquid waste.
ルミノシリケートを主成分とする無機物を充填した吸着
装置にアルカリ廃液をそのまま通水し、含有する放射性
核種を吸着除去することを特徴とする放射性廃液の処理
方法。6. A radioactivity characterized in that an alkaline waste liquid is directly passed through an adsorbing device filled with an inorganic material mainly composed of aluminosilicate composed of silicon, oxygen and aluminum to adsorb and remove a radionuclide contained therein. Waste liquid treatment method.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP19521391A JPH0534497A (en) | 1991-08-05 | 1991-08-05 | Process of radioactive waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP19521391A JPH0534497A (en) | 1991-08-05 | 1991-08-05 | Process of radioactive waste liquid |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0534497A true JPH0534497A (en) | 1993-02-09 |
Family
ID=16337346
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP19521391A Pending JPH0534497A (en) | 1991-08-05 | 1991-08-05 | Process of radioactive waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0534497A (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008536105A (en) * | 2005-03-16 | 2008-09-04 | ブリテイツシユ・ニユークリア・ヒユーエルズ・ピー・エル・シー | Waste disposal method |
| JP2012250904A (en) * | 2011-05-06 | 2012-12-20 | National Institute Of Advanced Industrial Science & Technology | Composite containing metal complex, and radiocesium adsorbent using the same |
| JP2013059717A (en) * | 2011-09-12 | 2013-04-04 | Toda Kogyo Corp | Ion adsorbent and method for producing the same |
| WO2013183742A1 (en) * | 2012-06-08 | 2013-12-12 | 協和化学工業株式会社 | Aluminum silicate and method for producing same |
| JP2014032031A (en) * | 2012-08-01 | 2014-02-20 | Kyoto Univ | Cesium-containing waste treatment method |
| JP2016114472A (en) * | 2014-12-15 | 2016-06-23 | 三菱重工業株式会社 | Radioactive waste liquid processing method and processing device for radioactive waste liquid |
-
1991
- 1991-08-05 JP JP19521391A patent/JPH0534497A/en active Pending
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008536105A (en) * | 2005-03-16 | 2008-09-04 | ブリテイツシユ・ニユークリア・ヒユーエルズ・ピー・エル・シー | Waste disposal method |
| JP2012250904A (en) * | 2011-05-06 | 2012-12-20 | National Institute Of Advanced Industrial Science & Technology | Composite containing metal complex, and radiocesium adsorbent using the same |
| JP2013059717A (en) * | 2011-09-12 | 2013-04-04 | Toda Kogyo Corp | Ion adsorbent and method for producing the same |
| WO2013183742A1 (en) * | 2012-06-08 | 2013-12-12 | 協和化学工業株式会社 | Aluminum silicate and method for producing same |
| CN104254493A (en) * | 2012-06-08 | 2014-12-31 | 协和化学工业株式会社 | Aluminum silicate and method for producing same |
| JPWO2013183742A1 (en) * | 2012-06-08 | 2016-02-01 | 協和化学工業株式会社 | Aluminum silicate and method for producing the same |
| TWI554473B (en) * | 2012-06-08 | 2016-10-21 | Kyowa Chem Ind Co Ltd | Method for reducing cesium ions |
| JP2014032031A (en) * | 2012-08-01 | 2014-02-20 | Kyoto Univ | Cesium-containing waste treatment method |
| JP2016114472A (en) * | 2014-12-15 | 2016-06-23 | 三菱重工業株式会社 | Radioactive waste liquid processing method and processing device for radioactive waste liquid |
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