JP2966569B2 - Separation method of cesium in uranium aqueous solution - Google Patents
Separation method of cesium in uranium aqueous solutionInfo
- Publication number
- JP2966569B2 JP2966569B2 JP11280991A JP11280991A JP2966569B2 JP 2966569 B2 JP2966569 B2 JP 2966569B2 JP 11280991 A JP11280991 A JP 11280991A JP 11280991 A JP11280991 A JP 11280991A JP 2966569 B2 JP2966569 B2 JP 2966569B2
- Authority
- JP
- Japan
- Prior art keywords
- aqueous solution
- cesium
- uranium
- uranium aqueous
- separation method
- 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.)
- Expired - Fee Related
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Treatment Of Liquids With Adsorbents In General (AREA)
- Water Treatment By Sorption (AREA)
Description
【０００１】[0001]
【産業上の利用分野】本発明は、核燃料再処理工程にお
けるウラン水溶液の精製方法に関し、核燃料取扱施設あ
るいは放射性同位元素実験施設から発生するセシウムを
含む廃液の精製技術にも適用可能な方法に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for purifying an aqueous uranium solution in a nuclear fuel reprocessing step, and more particularly to a method applicable to a purification technique for waste liquid containing cesium generated from a nuclear fuel handling facility or a radioisotope experimental facility.
【０００２】[0002]
【従来の技術】従来、ウラン水溶液中のセシウムの分離
技術としては溶媒抽出法および主に有機イオン交換体に
よる吸着分離法が用いられている。2. Description of the Related Art Conventionally, as a technique for separating cesium from an aqueous uranium solution, a solvent extraction method and an adsorption separation method mainly using an organic ion exchanger have been used.
【０００３】[0003]
【発明が解決しようとする課題】従来の技術には、各々
下記に問題点を有する。 （１）溶媒抽出法は通常液液抽出溶媒としてリンを含む
有機溶媒を使用するが、抽出にともない放射線により溶
媒が劣化し、大量の廃溶媒が発生する。この廃溶媒は通
常放射性廃棄物であって、その処理技術には多くの課題
を有している。また、この方法で高い分離度を得ようと
する場合には多段の抽出が必要であり、装置が大型化、
複雑化して高価となる。Each of the conventional techniques has the following problems. (1) In the solvent extraction method, an organic solvent containing phosphorus is usually used as a liquid-liquid extraction solvent, but the solvent is deteriorated by radiation due to the extraction, and a large amount of waste solvent is generated. This waste solvent is usually radioactive waste, and its processing technology has many problems. In addition, in order to obtain a high degree of separation by this method, multi-stage extraction is necessary, and the apparatus becomes large,
It becomes complicated and expensive.
【０００４】（２）イオン交換体による吸着分離法では
多くはイオン交換体として有機材料を使用している。こ
のため、有機溶媒と同様に放射線よる劣化が大きく、処
理の難しい放射性廃有機イオン交換体が発生する。ま
た、有機イオン交換体は一般に交換容量は大きいもの
の、交換する金属に対して選択性に乏しい。さらに、シ
リカゲル等の無機材料が使用されることも稀にあるが、
その吸着容量は小さく、ウラン水溶液中の微量セシウム
の吸着分離した例は見当たらない。(2) In the adsorption separation method using an ion exchanger, an organic material is often used as the ion exchanger. For this reason, similarly to the organic solvent, deterioration due to radiation is large, and a radioactive waste organic ion exchanger which is difficult to treat is generated. Further, the organic ion exchanger generally has a large exchange capacity, but has poor selectivity for a metal to be exchanged. In addition, inorganic materials such as silica gel are rarely used,
Its adsorption capacity is small, and there is no example of adsorption and separation of trace cesium in uranium aqueous solution.
【０００５】[0005]
【課題を解決するための手段】本発明は、前記従来の問
題点を解決すべくなされたものであり、ウラン水溶液の
ｐＨを０．２〜２．０に調整してゼオライト吸着剤と接
触させ、前記セシウムを前記吸着剤に吸着させることを
特徴とするウラン水溶液中のセシウムの分離方法であ
る。DISCLOSURE OF THE INVENTION The present invention has been made to solve the above-mentioned conventional problems, and adjusts the pH of an aqueous uranium solution to 0.2 to 2.0 to bring it into contact with a zeolite adsorbent. A method for separating cesium from an aqueous uranium solution, wherein the cesium is adsorbed on the adsorbent.
【０００６】本発明で使用するゼオライト吸着剤として
はモルデナイト型ゼオライト、ゼオライトＡ型、ゼオラ
イトＸ型、ゼオライトＹ型、ゼオライトＺＳＭ−５型な
どが使用しうる。As the zeolite adsorbent used in the present invention, mordenite zeolite, zeolite A type, zeolite X type, zeolite Y type, zeolite ZSM-5 type and the like can be used.
【０００７】[0007]
【作用】（１）ウラン水溶液のｐＨを０．２〜２．０に
調整することにより、液中の微量のセシウム吸着を高効
率で行え吸着容量が大きくなる。 （２）セシウムの分離を吸着操作で行うために、操作性
がよく装置がコンパクトにできる。 （３）使用する吸着剤が無機材料であり、放射線による
劣化が少なく、固体廃棄物としても固化体処理が容易で
ある。(1) By adjusting the pH of the uranium aqueous solution to 0.2 to 2.0, a small amount of cesium in the liquid can be adsorbed with high efficiency and the adsorption capacity can be increased. (2) Since cesium is separated by an adsorption operation, the operability is good and the apparatus can be made compact. (3) The adsorbent used is an inorganic material, is hardly deteriorated by radiation, and can be easily treated as a solid waste.
【０００８】[0008]
【実施例】本発明の一実施例で使用したウラン水溶液の
性状を以下に示す。 （Ａ）ウラン水溶液の性状（原液） ウラン濃度：４００×１０3 mg／１ セシウム濃度：５×１０-2mCi ／１（５．７×１０-4
mg／１） 酸濃度：０．６Ｎ−ＨＮＯ3 EXAMPLES The properties of the uranium aqueous solution used in one example of the present invention are shown below. (A) Properties of uranium aqueous solution (stock solution) Uranium concentration: 400 × 10 3 mg / 1 Cesium concentration: 5 × 10 −2 mCi / 1 (5.7 × 10 −4)
mg / 1) Acid concentration: 0.6N-HNO 3
【０００９】（Ｂ）調整したウラン水溶液の性状 ウラン水溶液をビン４個に分取し、３Ｎ−ＮａＯＨ水溶
液または５Ｎ−ＮａＯＨ水溶液を添加してｐＨを次のよ
うに調整したもので実施した。 サンプルＡ：ウラン水溶液 ０．６Ｎ−ＨＮＯ3 〔ｐ
Ｈ〕０ サンプルＢ：ウラン水溶液 〔ｐＨ〕０．２ サンプルＣ：ウラン水溶液 〔ｐＨ〕１．５ サンプルＤ：ウラン水溶液 〔ｐＨ〕２．０(B) Properties of the adjusted uranium aqueous solution The uranium aqueous solution was fractionated into four bottles, and the pH was adjusted as follows by adding a 3N-NaOH aqueous solution or a 5N-NaOH aqueous solution. Sample A: uranium aqueous solution 0.6N-HNO 3 [p
H] 0 Sample B: Uranium aqueous solution [pH] 0.2 Sample C: Uranium aqueous solution [pH] 1.5 Sample D: Uranium aqueous solution [pH] 2.0
【００１０】以下、図１に沿って説明する。サンプルＣ
を供試液槽１に貯液する。貯液したウラン水溶液を供給
ポンプ２を介して吸着塔３へ供給する。吸着塔３は内径
５０mmであり、モルデナイト型ゼオライト吸着剤が高さ
３００mmで充填してある。このとき、吸着剤重量は約９
００ｇであった。また、吸着塔３及び水溶液の温度は２
５±１℃に調整した。この吸着塔３に、１時間に約２．
０リットルのウラン水溶液を供給し、塔底より流出した
液を排出ポンプ４を介して処理液槽５へ導く。また、サ
ンプルＡ，Ｂ，Ｄのウラン水溶液についても同様の操作
を行う。Hereinafter, description will be given with reference to FIG. Sample C
Is stored in the test solution tank 1. The stored uranium aqueous solution is supplied to the adsorption tower 3 via the supply pump 2. The adsorption tower 3 has an inner diameter of 50 mm and is filled with a mordenite type zeolite adsorbent at a height of 300 mm. At this time, the weight of the adsorbent is about 9
00 g. The temperature of the adsorption tower 3 and the aqueous solution is 2
Adjusted to 5 ± 1 ° C. In this adsorption tower 3, about 2.
A uranium aqueous solution of 0 liter is supplied, and the liquid flowing out from the bottom of the column is guided to the processing liquid tank 5 via the discharge pump 4. The same operation is performed for the uranium aqueous solutions of Samples A, B, and D.
【００１１】なお、この実施例ではモルデナイト型ゼオ
ライトを約０．５mm直径を有する球状物に成形しマイク
ロビーズ吸着剤として使用した。In this example, mordenite-type zeolite was formed into a sphere having a diameter of about 0.5 mm and used as an adsorbent for microbeads.
【００１２】図２に、この実施例で得られたウラン水溶
液中のセシウム除去効果を吸着破過曲線で示した。図２
からも明らかなように、ウラン水溶液のｐＨを調整する
ことにより、セシウム吸着効果は大きく改善され、硝酸
酸性の強い（ウラン水溶液原液）場合と比べ、約５倍の
吸着能力を有していることがわかる。FIG. 2 shows the effect of removing cesium from the uranium aqueous solution obtained in this example by means of an adsorption breakthrough curve. FIG.
As is clear from the above, by adjusting the pH of the uranium aqueous solution, the cesium adsorption effect is greatly improved, and the adsorption capacity is about five times that of the case of strong nitric acid acidity (uranium aqueous solution stock solution). I understand.
【００１３】本発明によれば、実施例のごとくウラン水
溶液のｐＨを調整することにより、無機材料であり吸着
容量の小さいゼオライト吸着剤上に効率的に吸着させ、
ウラン水溶液中のセシウムを分離することが可能であ
る。According to the present invention, by adjusting the pH of the uranium aqueous solution as in the embodiment, the uranium aqueous solution is efficiently adsorbed on the zeolite adsorbent which is an inorganic material and has a small adsorption capacity.
Cesium in uranium aqueous solution can be separated.
【図１】本発明の一実施例の説明図。FIG. 1 is an explanatory diagram of one embodiment of the present invention.
【図２】本発明の実施例で得られた吸着破過曲線を示す
図表。FIG. 2 is a chart showing an adsorption breakthrough curve obtained in an example of the present invention.
Claims (1)
法において、前記ウラン水溶液のｐＨを０．２〜２．０
に調整してゼオライト吸着剤と接触させ、前記セシウム
を前記吸着剤に吸着させることを特徴とするウラン水溶
液中のセシウムの分離方法。1. A method for separating cesium from an aqueous uranium solution, wherein the pH of the aqueous uranium solution is from 0.2 to 2.0.
A method for separating cesium from an aqueous uranium solution, wherein the cesium is adsorbed on the adsorbent by contacting with a zeolite adsorbent.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11280991A JP2966569B2 (en) | 1991-05-17 | 1991-05-17 | Separation method of cesium in uranium aqueous solution |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11280991A JP2966569B2 (en) | 1991-05-17 | 1991-05-17 | Separation method of cesium in uranium aqueous solution |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH04340497A JPH04340497A (en) | 1992-11-26 |
| JP2966569B2 true JP2966569B2 (en) | 1999-10-25 |
Family
ID=14596076
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP11280991A Expired - Fee Related JP2966569B2 (en) | 1991-05-17 | 1991-05-17 | Separation method of cesium in uranium aqueous solution |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2966569B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2937634B1 (en) * | 2008-10-27 | 2011-09-30 | Commissariat Energie Atomique | METHOD FOR DECONTAMINATING A LIQUID EFFLUENT COMPRISING ONE OR MORE RADIOACTIVE CHEMICAL ELEMENTS BY FLUIDIZED BED TREATMENT |
| JP6218357B2 (en) * | 2012-03-08 | 2017-10-25 | 日立造船株式会社 | Method and apparatus for separating and removing radioactive cesium contained in waste water |
-
1991
- 1991-05-17 JP JP11280991A patent/JP2966569B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPH04340497A (en) | 1992-11-26 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A01 | Written decision to grant a patent or to grant a registration (utility model) |
Free format text: JAPANESE INTERMEDIATE CODE: A01 Effective date: 19990721 |
|
| LAPS | Cancellation because of no payment of annual fees |