JPS6065721A - Purification of rare earth element - Google Patents
Purification of rare earth elementInfo
- Publication number
- JPS6065721A JPS6065721A JP58173654A JP17365483A JPS6065721A JP S6065721 A JPS6065721 A JP S6065721A JP 58173654 A JP58173654 A JP 58173654A JP 17365483 A JP17365483 A JP 17365483A JP S6065721 A JPS6065721 A JP S6065721A
- Authority
- JP
- Japan
- Prior art keywords
- aqueous solution
- rare earth
- earth element
- solid materials
- chloride
- 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
Classifications
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01F—COMPOUNDS OF THE METALS BERYLLIUM, MAGNESIUM, ALUMINIUM, CALCIUM, STRONTIUM, BARIUM, RADIUM, THORIUM, OR OF THE RARE-EARTH METALS
- C01F17/00—Compounds of rare earth metals
- C01F17/20—Compounds containing only rare earth metals as the metal element
- C01F17/253—Halides
- C01F17/271—Chlorides
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Compounds Of Alkaline-Earth Elements, Aluminum Or Rare-Earth Metals (AREA)
Abstract
Description
【発明の詳細な説明】
本発明は塩化粘土の精製法に関jるものであり、詳しく
は塩化布上水溶液中の放射性物質の含有量を減少させる
方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for purifying chlorinated clay, and more particularly to a method for reducing the content of radioactive substances in a chlorinated cloth aqueous solution.
塩化希土水溶液は種々の粘土製品の中間体であり、一般
にモナズ石等の鉱石を分解して得られる粗水酸化粘土を
塩酸に溶解することにより調製される。このようにして
得られる塩化布上水溶液中には、鉱石に由来するラジウ
ムを主体とする放射性物質が溶存している。放射性物質
?含む粘土はその部品価値か着るしく低下するので、そ
の含有量1文極力低減させることが好ましい。Rare earth chloride aqueous solutions are intermediates for various clay products, and are generally prepared by dissolving crude hydroxide clay obtained by decomposing ores such as monazite in hydrochloric acid. Radioactive substances mainly composed of radium derived from ores are dissolved in the chlorinated cloth aqueous solution obtained in this way. Radioactive material? It is preferable to reduce the content of clay by as much as possible, since the value of the parts decreases considerably.
水溶液から溶存しているラジウム化合物ケ除去する方法
としては、水溶液にバリウムイオンおよび硫酸イオンを
添加して硫酸バリウムを生成させ、これにラジウム化合
物を同伴させて沈降させる方法か知られている。しかし
ながら、上述のようなモナズ石等の鉱石乞分解して得た
粗水酸化粘土から調製した塩化希土水溶液にこの方法ン
適用しても、放射付物質ケ満足1−べき程度に除去する
ことはできないことが判明した。A known method for removing dissolved radium compounds from an aqueous solution is to add barium ions and sulfate ions to an aqueous solution to generate barium sulfate, which is then accompanied by a radium compound to precipitate. However, even when this method is applied to an aqueous rare earth chloride solution prepared from crude hydroxide clay obtained by decomposing ores such as monazite, it is difficult to remove radioactive substances to a satisfactory extent. It turned out that it was not possible.
本発明者らはこの原因について検討した結果、塩化布上
水溶液中に懸濁している固形物7予じぬ除去しておくこ
とにより、含有されている放射性物質を効率よく除去す
ることかできること乞見出した。The inventors of the present invention investigated the cause of this problem, and found that it is possible to efficiently remove the radioactive substances contained therein by unexpectedly removing the solid matter 7 suspended in the aqueous solution on the chloride cloth. I found it.
本発明はこのような知見に基づいて完成されたもので、
その要旨は、固形物が共存しておりかつ可溶性放射性物
質を含有する塩化布上水溶液から、固形物の存在量が0
./重量%以下となるまで固形物を除去したのち、これ
にバリウムイオンおよび硫酸イオンを添加して硫酸塩を
析出させ、次いで水溶液からこれらの固形物を除去する
ことにより放射性物質の含量を低減させることケ特徴と
する塩化粘土の精製法に存する。The present invention was completed based on such knowledge,
The gist of this is that from a chlorinated cloth aqueous solution containing coexisting solids and soluble radioactive materials, the amount of solids present is 0.
.. /wt% or less, barium ions and sulfate ions are added to this to precipitate sulfate, and then these solids are removed from the aqueous solution to reduce the content of radioactive substances. The main feature lies in the method for refining chloride clay.
本発明についてさらに詳細に説明すれば、本発明で塩化
粘土とは、原子番号37〜7ノの元素ならびにイツトリ
ウムおよびスカンジウムを含む元素群の塩化物を指すも
のである。塩化布上水溶液は通常、モナズ石のような鉱
石をアルカリ分解して得られた水酸化粘土またはアルカ
1;
りの代りl鉱石を硫酸で分解したのち分解物をアルカリ
で苛性化して得られた水酸化粘土を、塩酸に溶解するこ
とにより調製される。また、このようにして得られた塩
化布上水溶液に種々の精製手段を施して、一部の不純物
や元素等を予じめ除去しておいてもよい。To explain the present invention in more detail, the term chlorinated clay in the present invention refers to chlorides of elements having an atomic number of 37 to 7, as well as an element group including yttrium and scandium. The aqueous chloride solution is usually a hydroxide clay obtained by alkaline decomposition of an ore such as monazite or alkali; Prepared by dissolving hydroxide clay in hydrochloric acid. Further, the chlorinated cloth aqueous solution obtained in this manner may be subjected to various purification means to remove some impurities, elements, etc. in advance.
これらの塩化希生水溶液中には一般に微細な固形物が共
存している。これは主に原料の水酸化希土中に混在して
いた不純物でル・ろが、場合によっては塩化粘土水溶液
から析出した固形物が含まれていることもある。また、
鉱石に由来する放射性物質が水溶液中に微ht溶存して
おり、その主成分はラジウムであると推定さえ1.てい
イ)。Fine solid matter generally coexists in these dilute chloride aqueous solutions. This is mainly impurities mixed in the raw material rare earth hydroxide, and in some cases it may also contain solid matter precipitated from the aqueous chloride clay solution. Also,
Radioactive substances derived from ores are dissolved in aqueous solution, and it is estimated that the main component is radium.1. (teii).
本発明方法では、先ずこのような微に111な固形物お
よび可溶性放射性物質を含有量ろ塩化布上水溶液から、
フィルタープレスや遠心分離機その他の固液分離手段に
より、水溶液中の固形物含量が0− ’ i! #係以
下、好ましくはθθs−M< j;;係以下となるよう
に固形物を除去1−ろ。固形物の含有量が0./重量%
より4.多いと、次の工程で放射性物質な十分に除去1
−ることかできない、。In the method of the present invention, such slightly 111 solids and soluble radioactive substances are first extracted from an aqueous solution on a chlorinated cloth.
By using a filter press, centrifuge, or other solid-liquid separation means, the solid content in the aqueous solution can be reduced to 0-' i! 1-filter to remove solids so that the ratio is less than #, preferably less than θθs-M<j; Solid content is 0. /weight%
From 4. If there is too much, radioactive substances will be removed in the next process1.
-I just can't do it.
一般に固形物の含刹量が少ないほど放射性物1g(の除
去は良好なので、装置4能力の計1−限りその含有量を
低減させるのが好ましい3、
固形物を除去した塩化布上水溶液には、次いでバリウム
イオンおよび硫酸イオン欠添加して、硫酸バリウムを生
成させる。通常は塩化布上水溶液のP Hi Q −5
とし、攪拌しながらこれにバリウムイオンおよび硫酸イ
オンを順次添加すればよい。In general, the smaller the amount of solids contained, the better the removal of 1 g of radioactive materials, so it is preferable to reduce the content as far as the total capacity of the 4 devices 3. , then barium ions and sulfate ions are added to form barium sulfate.Usually, P Hi Q -5 of an aqueous solution of chloride cloth is added.
barium ions and sulfate ions may be sequentially added thereto while stirring.
バリウムイオン源としては、塩化バリウム、炭酸バリウ
ム等の酸に可溶のバリウム塩が用いられる。また硫酸イ
オン源としては硫酸や硫酸アンモニウム、硫酸ナトリウ
ム等の酸に可溶の硫酸塩が用いられる。また可溶性の硫
酸粘土を用いることもできる。バリウムイオンの添加量
は、塩化希出水溶液/l当りバリウムとして通常0.
/ −5g、好ましくはo、s〜コ、Sgである。As the barium ion source, acid-soluble barium salts such as barium chloride and barium carbonate are used. As the sulfate ion source, sulfates soluble in acids such as sulfuric acid, ammonium sulfate, and sodium sulfate are used. It is also possible to use soluble sulfuric acid clay. The amount of barium ion added is usually 0.00 barium per liter of diluted chloride aqueous solution.
/ -5g, preferably o, s to co, Sg.
また、硫酸イオンはバリウムイオンとほぼ当量となるよ
うに添加すればよいが、過剰に添加しても差支えない。Further, sulfate ions may be added in an amount approximately equivalent to that of barium ions, but may be added in excess.
バリウムイオンおよび硫酸イオンを添加して硫酸バリウ
ムを生成させた塩化布上水溶液は、次いでフィルタープ
レス、遠心分離機ソの他1)適宜の固液分離手段により
、存在する固形物乞除去1−る。このとき放射性物質も
同時pr除去されるので、放射性物質の含有量の著るし
く低減された塩化布上水溶液が回収されろ。The aqueous chloride cloth solution to which barium ions and sulfate ions have been added to produce barium sulfate is then passed through a filter press, centrifuge, or other appropriate solid-liquid separation means to remove any solid particles present. . At this time, radioactive substances are also removed at the same time, so a chlorinated cloth aqueous solution with a significantly reduced content of radioactive substances can be recovered.
以下に実施例により本発明をさらにリ一体的Vσ説明す
るか1本発明はその要旨を超えない限り、以下の実施例
に駆足されるものではない。Hereinafter, the present invention will be further explained with reference to the examples.The present invention is not intended to be exhaustive by the following examples unless it goes beyond the gist of the present invention.
なお、以下の実施例および比較例において、塩化希土水
溶液中の固形物量は、安武科堂轡誠■製の遠心沈降機H
−100型を用いて、lθOOaで70分間遠心沈降し
た際に分離された固形物量である。また放射能量はアロ
ヵ■製の放射能測定装置TDO−10,3型を用いて測
定した値である。In addition, in the following Examples and Comparative Examples, the amount of solids in the rare earth chloride aqueous solution was measured using a centrifugal sedimentator H manufactured by
This is the amount of solid matter separated during centrifugal sedimentation at lθOOa for 70 minutes using the -100 type. Moreover, the amount of radioactivity is a value measured using a radioactivity measuring device TDO-10,3 type manufactured by Aloka ■.
実施例/
モナズ石を水酸化ナトリウムを用いて分解して、セリウ
ム約SO%、ランタン約2s%、その他動2S%からな
る粗水酸化布上とし、これ乞塩酸に溶解してPH3,!
;の塩化布上水溶液を調製した。この水溶液の布上濃度
は酸化物(R2O3)換算で約72%であり、固形物乞
約O,S%含イ1していた。この塩化希土水溶液をフィ
ルタープレスを用いて濾過し、その固形物含有量を0.
0q%にまで減少させた。攪拌しながらこれに塩化ハI
Jウムの10%水溶液を添加しく添加量はバリウムとし
て/、 7 Vl )、次いで硫酸アンモニウムの7O
%水溶液を添加した(添加量はバリウムに対し7.5当
量)。フィルタープレスを用いて濾過し、生成した硫酸
バリウムを除去した。P液は蒸発濃縮したのち冷却して
固体の塩化希±(乙水塩)とした。この塩化布上の放射
能量は9 X / 0″4μC1/gであった。Example: Monazite was decomposed using sodium hydroxide to form a crude hydroxide cloth consisting of about SO% cerium, about 2s% lanthanum, and 2S% other moieties, which was then dissolved in hydrochloric acid to pH 3,!
An aqueous solution of chloride on cloth was prepared. The concentration of this aqueous solution on the cloth was about 72% in terms of oxides (R2O3), and it contained about 1% of solids. This rare earth chloride aqueous solution was filtered using a filter press to reduce the solid content to 0.
It was reduced to 0q%. Add hydrogen chloride to this while stirring.
Add a 10% aqueous solution of ammonium sulfate (the amount added is barium/7 Vl), then add 7O of ammonium sulfate.
% aqueous solution (the amount added was 7.5 equivalents to barium). It was filtered using a filter press to remove the generated barium sulfate. The P solution was evaporated and concentrated and then cooled to form a solid diluted chloride (water salt). The amount of radioactivity on this chlorinated cloth was 9×/0″4 μC1/g.
比較例/
実施例/において、θ、s係の固形物を含有する塩化希
上水溶液から固形物の除去を行なわない以外は、実施例
1と全く同様して塩化希±(ろ水塩)を得た。このもの
の放射能量はl×70−2μC179であった。In Comparative Example/Example/, diluted chloride (filtrate salt) was prepared in exactly the same manner as in Example 1, except that solids were not removed from the diluted chloride aqueous solution containing solids in the θ and s groups. Obtained. The amount of radioactivity of this product was lx70-2μC179.
代理人→を圧出 長谷用 −Extract agent → for Hase −
Claims (1)
含有する塩化希上水溶液から、固形物の存在量がo、i
重量製以下となるまで固形物を除去したのち、これにバ
リウムイオンおよび硫酸イオンを添加して硫酸塩を析出
させ、次いで水溶液からこれらの固形物を除去すること
により放射性物質の含量を低減させることを特徴とする
塩化粘土の精製法。(1) From a dilute aqueous chloride solution containing solids and soluble radioactive substances, the amount of solids present is o, i.
After removing solids until the weight of the solution is less than that, barium ions and sulfate ions are added to precipitate sulfate, and then these solids are removed from the aqueous solution to reduce the content of radioactive substances. A method for refining chloride clay characterized by:
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58173654A JPS6065721A (en) | 1983-09-20 | 1983-09-20 | Purification of rare earth element |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58173654A JPS6065721A (en) | 1983-09-20 | 1983-09-20 | Purification of rare earth element |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6065721A true JPS6065721A (en) | 1985-04-15 |
Family
ID=15964621
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP58173654A Pending JPS6065721A (en) | 1983-09-20 | 1983-09-20 | Purification of rare earth element |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6065721A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2750414A1 (en) * | 1996-07-01 | 1998-01-02 | Rhone Poulenc Chimie | Treatment of mixture comprising rare earth, radium , thorium and uranium |
CN1077546C (en) * | 1998-06-04 | 2002-01-09 | 葛新芳 | Method for producing mixed rare-earth chloride |
FR2913970A1 (en) * | 2007-03-19 | 2008-09-26 | Cogema | PRODUCTION OF THORIUM 228 FROM A NATURAL THORIUM SALT |
-
1983
- 1983-09-20 JP JP58173654A patent/JPS6065721A/en active Pending
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2750414A1 (en) * | 1996-07-01 | 1998-01-02 | Rhone Poulenc Chimie | Treatment of mixture comprising rare earth, radium , thorium and uranium |
CN1077546C (en) * | 1998-06-04 | 2002-01-09 | 葛新芳 | Method for producing mixed rare-earth chloride |
FR2913970A1 (en) * | 2007-03-19 | 2008-09-26 | Cogema | PRODUCTION OF THORIUM 228 FROM A NATURAL THORIUM SALT |
WO2008113792A3 (en) * | 2007-03-19 | 2008-11-13 | Areva Nc | Production of thorium 228 starting from a natural thorium salt |
US8221520B2 (en) | 2007-03-19 | 2012-07-17 | Areva Nc | Production of thorium 228 starting from a natural thorium salt |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US4168296A (en) | Extracting tungsten from ores and concentrates | |
US5433931A (en) | Recovery of cerium | |
RU2408534C2 (en) | Method of preparing caesium hydroxide solutions | |
US20150136704A1 (en) | Method and apparatus for treating wastewater containing radioactive strontium | |
RU2114204C1 (en) | Method of recovering cerium | |
US2433601A (en) | Preparation of purified brine | |
CA2147059C (en) | Magnesium-enhanced sulfur dioxide scrubbing with gypsum formation | |
US5034201A (en) | Recovery of rare earth values from gypsum | |
JP4375630B2 (en) | Method of solubilizing valuable metal from Ta-Nb-ore material containing insoluble fluoride | |
JPS6065721A (en) | Purification of rare earth element | |
US2384009A (en) | Process for recovering magnesium salts | |
EP0189831B1 (en) | Cobalt recovery method | |
AU2017408055B2 (en) | Method for removing fluoride from a zinc-containing solution or suspension, defluoridated zinc sulfate solution and use thereof, and method for producing zinc and hydrogen fluoride or hydrofluoric acid | |
WO2005068358A1 (en) | Production of 'useful material(s)' from waste acid issued from the production of titanium dioxyde | |
JP2890830B2 (en) | Purification method of scandium oxide | |
CA1094812A (en) | Preparation of ferric iron solutions | |
JP2994405B2 (en) | Purification method of alkali hydroxide | |
JPS5839894B2 (en) | Method for removing phosphorus and silicon from water-soluble smelting slag | |
US2398743A (en) | Recovery of magnesium compounds | |
US2342666A (en) | Recovering magnesium salts | |
US3849535A (en) | Method for recovery of elements and compounds from aqueous solutions | |
US3057682A (en) | Process for recovery as zirconium oxysulfate zirconium values from salt baths | |
US3671187A (en) | Removal of dissolved lead from alkali metal chloride containing solutions | |
SU882937A1 (en) | Method of separating magnetite | |
JP3717873B2 (en) | Method for recovering cerium from chromium etchant |