JPS5930651B2 - How to recover uranium - Google Patents
How to recover uraniumInfo
- Publication number
- JPS5930651B2 JPS5930651B2 JP57087187A JP8718782A JPS5930651B2 JP S5930651 B2 JPS5930651 B2 JP S5930651B2 JP 57087187 A JP57087187 A JP 57087187A JP 8718782 A JP8718782 A JP 8718782A JP S5930651 B2 JPS5930651 B2 JP S5930651B2
- Authority
- JP
- Japan
- Prior art keywords
- uranium
- magnetic separator
- slurry
- calcium fluoride
- valve
- 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
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0208—Obtaining thorium, uranium, or other actinides obtaining uranium preliminary treatment of ores or scrap
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
- C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
- C22B60/0239—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agent
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
- C22B60/0247—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using basic solutions or liquors
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
- C22B60/026—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
- C22B60/0265—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Manufacturing & Machinery (AREA)
- Environmental & Geological Engineering (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Description
【発明の詳細な説明】
発明の分野
本発明は水性フッ化カルシウムスラリからウランを回収
する方法に関する。DETAILED DESCRIPTION OF THE INVENTION Field of the Invention This invention relates to a method for recovering uranium from an aqueous calcium fluoride slurry.
発明の背景
米国特許第２９６５４４０号は鉄を含む鉱石からウラン
の回収について開示している。BACKGROUND OF THE INVENTION US Pat. No. 2,965,440 discloses the recovery of uranium from iron-bearing ores.
鉱石を適当な粒子径に磨砕し、次いでウラン−鉄錯体を
生ずるように焙焼する。The ore is ground to the appropriate particle size and then roasted to form a uranium-iron complex.
錯体中に鉄が存在する点を考えれば、鉱石の残渣から錯
体を磁気的に分離することが可能である。Given the presence of iron in the complex, it is possible to magnetically separate the complex from the ore residue.
粉末酸化ウラン生成用のニララン酸アンモニウム変換プ
ロセスにおいては、ウラン、フッ化物、アンモニウム、
及び硝酸塩のそれぞれイオンを含む廃水を生ずる。The ammonium niralanate conversion process for the production of powdered uranium oxide involves the use of uranium, fluoride, ammonium,
and nitrate ions, respectively.
アンモニアを回収し、フッ化物の濃度を下げるために、
水酸化カルシウム又は石灰スラリを加えてフッ化カルシ
ウムを沈殿させる。To recover ammonia and reduce fluoride concentrations,
Calcium hydroxide or lime slurry is added to precipitate calcium fluoride.
ニララン酸アンモニウム廃水はアンモニア１１離塔で処
理し、生成したフッ化カルシウムスラリは沈殿池に送ら
れ、ここで過剰の水をデカントし廃棄する。The ammonium nylaranate wastewater is treated in an ammonia 11 separate tower, and the resulting calcium fluoride slurry is sent to a settling basin where excess water is decanted and disposed of.
ウランは不溶性ウラン酸カルシウムであるフッ化カルシ
ウムスラリ中に多少残る。Some uranium remains in the calcium fluoride slurry, which is insoluble calcium uranate.
このウラン酸カルシウム廃棄物は費用のかかる廃棄物処
理問題をひき起すばかりでなく、有用な資源の損失でも
ある。This calcium uranate waste not only creates an expensive waste disposal problem, but is also a loss of useful resources.
特公昭４８−３８３２０号か開示しているようなウラン
の他の回収方法は、フッ化カルシウムが沈殿する前の廃
水からウランを除去しているが、この方法はフッ化カル
シウムスラリかすでに存在する大沈殿池からウランを回
収するには役に立たない。Other uranium recovery methods, such as those disclosed in Japanese Patent Publication No. 48-38320, remove uranium from wastewater before calcium fluoride precipitates; It is useless for recovering uranium from large sedimentation ponds.
発明の開示
本発明は、鉄１００１）１１１１以下を含むフッ化カル
シウム水性スラリからウランを回収する方法において、
該スラリを高勾配磁気分離器に通過し、次いで該分離器
からウランを除去する工程を含む、ウランの回収方法に
存する。DISCLOSURE OF THE INVENTION The present invention provides a method for recovering uranium from an aqueous calcium fluoride slurry containing iron 1001) 1111 or less.
A method for recovering uranium includes passing the slurry through a high gradient magnetic separator and then removing uranium from the separator.
この方法は単純であまり高価でなく、多大な資金を必要
とせず、現存のウランプロセスに直接添加できるウラン
生成物を製造することを可能としたものである。This process is simple and inexpensive, does not require large amounts of capital, and makes it possible to produce a uranium product that can be added directly to existing uranium processes.
以下、図を参照して実施態様に基き本発明をさらに詳細
に説明する。Hereinafter, the present invention will be explained in more detail based on embodiments with reference to the drawings.
実施態様の説明
第１図を参照すると、分散剤１を配管２中のフッ化カル
シウムスラリに加える。DESCRIPTION OF THE EMBODIMENTS Referring to FIG. 1, dispersant 1 is added to the calcium fluoride slurry in line 2.
このスラリは大きな粒子を砕くボールミル３を通過し、
次いでポンプ４によりスラリをサイクロン式分離器５に
送り、ここでスラリから大きな粒子を分離し、この大き
な粒子はりザイクル管６でリサイクルし、細かい粒子を
バルブ８及び配管７を通して高勾配磁気分離器９へ導入
する。This slurry passes through a ball mill 3 that crushes large particles.
The slurry is then sent by a pump 4 to a cyclone separator 5, where large particles are separated from the slurry, recycled through a cycle tube 6, and fine particles are passed through a valve 8 and piping 7 to a high gradient magnetic separator 9. to be introduced.
磁気分離器９は電磁石の磁極１１及び１２の間に多孔質
強磁性介在物１３を含む鉄製容器１０から成る。The magnetic separator 9 consists of an iron container 10 containing a porous ferromagnetic inclusion 13 between the magnetic poles 11 and 12 of the electromagnet.
フッ化カルシウムスラリか磁気分離器９を通過する時、
スラリ中のウランは多孔質強磁性介在物に付着する。When the calcium fluoride slurry passes through the magnetic separator 9,
The uranium in the slurry adheres to porous ferromagnetic inclusions.
残りのスラリは検出器１４へ送られ、この検出器１４は
分離器がウランで飽和するとウランか今分離器を通った
ことを示す信号を発する。The remaining slurry is passed to a detector 14 which, when the separator is saturated with uranium, emits a signal indicating that uranium has now passed through the separator.
次いでスラリはバルブ１５を通過し、水を除去するスラ
ッジ脱水器１６に送られる。The slurry then passes through valve 15 and is sent to sludge dewaterer 16 where water is removed.
このスラリの残部は廃棄スラッジとなる。The remainder of this slurry becomes waste sludge.
磁気分離器がウランで飽和したことを検出器か示した時
には配管１７中の炭酸塩抽出溶液が磁気分離器に導入さ
れ、多孔質強磁性介在物に付着したウランを溶解するた
めにバルブ８及び１５を回す。When the detector indicates that the magnetic separator is saturated with uranium, the carbonate extraction solution in line 17 is introduced into the magnetic separator and valves 8 and Turn 15.
ウランを含んだ炭酸塩抽出溶液はバルブ１５及び配管１
８を通過して、存在することがある大きな粒子を除去す
る（バックフラッシュ）フィルター１９へ導かれる。The carbonate extraction solution containing uranium is supplied through valve 15 and pipe 1.
8 and is directed to a filter 19 which removes (backflush) large particles that may be present.
溶解したウランは配管２０を通してイオン交換カラム２
１へ導かれ、ここでウランはイオン交換される。The dissolved uranium passes through the pipe 20 to the ion exchange column 2.
1, where the uranium is ion-exchanged.
この過程での循環流はポンプ２２で行われる。Circulating flow in this process is performed by the pump 22.
炭酸塩抽出が終了し、バルブ８及び１５を回してフッ化
カルシウムスラリか再び磁気分離器に流入すると、ポン
プ２３を使用しフィルタを通過したスラッジ脱水器１６
からの水流でフィルター１９は清浄に洗浄される。When the carbonate extraction is finished and the calcium fluoride slurry flows into the magnetic separator again by turning the valves 8 and 15, the sludge that has passed through the filter using the pump 23 is removed from the sludge dehydrator 16.
The filter 19 is cleanly washed by the water flow.
本発明の他の実施態様においては磁気分離器からウラン
を除去するために硝酸を使用し、且つ連続的なバッチ処
理を行うために２つの分離器を使用する。Other embodiments of the invention use nitric acid to remove uranium from a magnetic separator and use two separators to provide continuous batch processing.
第２図において、フッ化カルシウムスラリは配管３０か
ら磁気分離器３２のバルブ３１を通過し、次いでバルブ
３３及び配管３４から貯蔵池に至る。In FIG. 2, the calcium fluoride slurry passes from line 30 through valve 31 of magnetic separator 32 and then via valve 33 and line 34 to a storage pond.
一方、配管３５中の硝酸はバルブ３６を通って磁気分離
器３７へ導かれ、磁気分離器中の多孔質強磁性介在物上
のウランを溶解する。Meanwhile, nitric acid in pipe 35 is led through valve 36 to magnetic separator 37 to dissolve uranium on porous ferromagnetic inclusions in the magnetic separator.
溶解したウランはバルブ３８及び配管３９を通過し、溶
媒抽出器へ送られる。The dissolved uranium passes through valve 38 and piping 39 and is sent to the solvent extractor.
磁気分離器３２がウランで飽和した時、バルブ３Ｌ３３
，３６及び３８が閉じられ、バルブ４０，４１，４２及
び４３か開かれる。When the magnetic separator 32 is saturated with uranium, the valve 3L33
, 36 and 38 are closed and valves 40, 41, 42 and 43 are opened.
この時硝酸は配管３５、バルブ４０を通って磁気分離器
３２中のウランを溶解し、次いでバルブ４１を通って外
部へ配管３９へ送られろ。At this time, the nitric acid passes through the pipe 35 and the valve 40 to dissolve the uranium in the magnetic separator 32, and then passes through the valve 41 and is sent to the outside to the pipe 39.
フッ化カルシウムスラリはバルブ４２を通って磁気分離
器３７中に入り、バルブ４３を通って外部への配管３４
へ送られろ。The calcium fluoride slurry enters the magnetic separator 37 through valve 42 and into the external piping 34 through valve 43.
Be sent to.
初期のフッ化カルシウムスラリは、少くとも９５重量係
がフッ化カルシウムである固体を１〜１０％含み、残り
は水、及び通常ウラン酸カルシウムの数種の形態のウラ
ン１〜１ｏｏｏｐｐｍを含む。The initial calcium fluoride slurry contains 1-10% solids with at least 95% by weight calcium fluoride, the balance containing water and 1-100 ppm of uranium, usually in some form of calcium uranate.
これらのスラリ中のウランはウラン２３５か多く、特に
価値あるものである。The uranium in these slurries is uranium-235, which is particularly valuable.
一般に、本発明は不溶性ウラン化合物を含んだフッ化カ
ルシウムの液体スラリを使用する。Generally, the present invention uses a liquid slurry of calcium fluoride containing insoluble uranium compounds.
鉄はウランと共に溶解すると次後のプロセスでウランを
汚染することとなるので、上記スラリ中に存在する鉄は
１００ｐｐＩＩｌ・以下でなければならない。The amount of iron present in the slurry must be less than 100 ppIIl, since iron, if dissolved with uranium, will contaminate the uranium in subsequent processes.
このような汚染の場合、鉄からウランを分離するために
六フフ化ウランの形であるウランを再処理する必要があ
る。Such contamination requires reprocessing the uranium, in the form of uranium hexafluoride, to separate it from the iron.
しかし鉄が存在しない場合は、本発明による生成物は直
接溶媒抽出プロセスに導かれる。However, in the absence of iron, the products according to the invention are passed directly to a solvent extraction process.
フッ化カルシウムの大きな粒子を細かくするのを助ける
ためにフッ化カルシウムを分散剤を加えてもよい。A dispersant may be added to the calcium fluoride to help break down large particles of calcium fluoride.
分散剤は洗浄剤、例えばナックリン−ホルムアルデヒド
縮合物の硫酸すｌ−ＩＪウム塩、縮合有機酸中の５〜８
ｆｏの硫酸ナトＩＪウム塩、及びアルキル−アリールタ
イプの硫酸の錯重合有機塩を含む。The dispersant is a detergent, for example, a sulfuric acid salt of a nuclin-formaldehyde condensate, a 5 to 8
Contains sodium fo sulfate salt and complex organic salt of alkyl-aryl type sulfuric acid.
好適な分散剤はステパンケミカルカンパニイ（Ｓｔｅｐ
ａｎ Ｃｈｅｍｉｃａｌ Ｃｏｍｐａｎｙ）製゛ス
テペンクンＡ（Ｓ ｔｅｐａｎｔａｎ Ａ ） ” （
商品名）のナフタリン−ホルムアルデヒド縮合生成物の
硫酸すｌ−ＩＪウム塩である。A suitable dispersant is manufactured by Stepan Chemical Company (Step
``Stepantan A'' manufactured by An Chemical Company)
It is a sulfuric acid salt of a naphthalene-formaldehyde condensation product (trade name).
所望により分散剤０．０１〜０．０２重量係を使用して
もよい。If desired, 0.01 to 0.02 weight percent of the dispersant may be used.
大きな粒子が存在する場合にだけボールミル又はスラリ
中の粒子径を小さくする他の手段か必要である。Ball milling or other means of reducing particle size in the slurry is necessary only when large particles are present.
好適にはスラリ中の粒子径は約５ミクロン以下である。Preferably the particle size in the slurry is about 5 microns or less.
電磁石下のベルト上を通過する時にスラリ中の粒子が強
力な電磁石により押し出される通常の磁気分離と異なり
、本発明方法では急勾配の磁気分離器の使用が必要であ
る。Unlike conventional magnetic separation, where particles in a slurry are pushed out by a powerful electromagnet as they pass over a belt beneath an electromagnet, the method of the present invention requires the use of a steep magnetic separator.
急勾配磁気分離器においては２磁極間の間隔は約７．６
ＣＩＩ′Ｌ（３インチ）以下で、その空隙は多孔質強磁
性介在物を充填する。In a steep gradient magnetic separator, the spacing between two magnetic poles is approximately 7.6
Below CII'L (3 inches), the void is filled with porous ferromagnetic inclusions.
この分離器には非常に弱い磁性体であるウラン粒子を除
去するために１０キロガウス以上の磁場が必要である。This separator requires a magnetic field of 10 kilogauss or more to remove uranium particles, which are extremely weakly magnetic.
一般に７５キロワット以上の電力か必要で、電磁石のコ
イルの直径は４０α以下にすべきである。Generally, more than 75 kilowatts of power is required, and the diameter of the electromagnet coil should be less than 40 α.
代表的な磁気分離器は１時間当り固体原料３トンを処理
する。A typical magnetic separator processes 3 tons of solid feed per hour.
磁気分離器はウラン酸カルシウム、例えばＣａＵＯ４粒
子を、５０チ以上の多孔度を有する介在物上で捕獲する
。The magnetic separator captures calcium uranate, eg CaUO4 particles, on inclusions having a porosity of 50 square meters or more.
硝酸を使用しない場合は介在物はスチールウールで造る
ことかできるか、硝酸を使用する場合にはスチールウー
ルは硝酸に侵食されるのでステンレススチールウールが
必要である。If nitric acid is not used, the inclusions can be made of steel wool, or if nitric acid is used, stainless steel wool is required since steel wool is attacked by nitric acid.
フッ化カルシウムスラリは、磁気分離器かウランで飽和
しウランかまだ磁気分離器を通過していることを検出器
が示すまで、磁気分離器中を通過する。The calcium fluoride slurry passes through the magnetic separator until the magnetic separator is saturated with uranium and a detector indicates that uranium is still passing through the magnetic separator.
適当な検出器はガイガーカウンタヌは同様な装置である
が、螢光検出器がウランに対する感度が最も良いので好
適である。Suitable detectors include Geiger counters and similar devices, although fluorescence detectors are preferred as they are most sensitive to uranium.
磁気分離器を通過する流速は、流速が速いとウランが介
在物を押し流すかもしれないので、３７．９１／分（１
０ガロン／分）以下にすべきである。The flow rate through the magnetic separator is 37.91/min (1
(0 gallons/minute) or less.
磁気分離器中の介在物からのウランの除去は神様の手段
により可能である。Removal of uranium from inclusions in magnetic separators is possible by divine means.
例えば、はとんどの２〜５モルの炭酸塩溶液は磁気分離
器中のウランを溶解する。For example, most 2-5 molar carbonate solutions will dissolve uranium in a magnetic separator.
ナトリウムは他のアルカリ金属の炭酸塩が使用できろが
、次後のプロセスにより適合できる炭酸アンモニウムが
好適である。Although other alkali metal carbonates can be used as sodium, ammonium carbonate is preferred as it is more compatible with subsequent processes.
しかし、好適なウラン除去法は硝酸水溶液での逆洗浄で
ある。However, the preferred uranium removal method is backwashing with aqueous nitric acid.
この硝酸洗浄はフッ化カルシウムの溶解を避けるために
ｐＨは約２以上で、且つウランを溶解しないようにｐＨ
は約３以下とする必要がある。In this nitric acid cleaning, the pH is approximately 2 or higher to avoid dissolving calcium fluoride, and the pH is adjusted to avoid dissolving uranium.
must be approximately 3 or less.
硝酸を使用した場合、浸出液は使用する溶媒抽出系、例
えば当業界で周知である、ケロシンのような有機溶媒中
のジー２−エチルへキシルリン酸−トリオクチルホスフ
ィンオキシド（ＤＥＰＡ−ＴＯＰＯ）抽出系に直接流入
させろことができろ。When nitric acid is used, the leachate is subjected to the solvent extraction system used, such as di-2-ethylhexyl phosphate-trioctylphosphine oxide (DEPA-TOPO) extraction system in an organic solvent such as kerosene, which is well known in the art. You can let it flow in directly.
炭酸塩溶液を使用した場合、当業界で周知のように、ウ
ランはイオン交換カラム中で炭酸塩溶液から除去するこ
とかできる。If a carbonate solution is used, uranium can be removed from the carbonate solution in an ion exchange column, as is well known in the art.
次に、ウランはイオン交換カラムから硝酸溶液により除
かれ、この不肖酸溶液は溶媒抽出工程へ送られろ。The uranium is then removed from the ion exchange column with a nitric acid solution, and the unfriendly acid solution is sent to a solvent extraction step.
このように、イオン交換カラムでの抽出の余分なプロセ
スは、硝酸を磁気分離器からのウラン除去に使用した場
合には必要でない。Thus, the extra process of extraction with an ion exchange column is not required when nitric acid is used for uranium removal from a magnetic separator.
次に実施例に基き本発明を説明する。Next, the present invention will be explained based on examples.
実施例 ゛
ステンレススチールウール介在物を含み第１図に示す磁
気分離器に、固体フッ化カルシウム２係及びウラン酸カ
ルシウムとしてウラン１５ｐｐｍを含む水溶性フッ化カ
ルシウム溶液を通過させた。EXAMPLE An aqueous calcium fluoride solution containing solid calcium fluoride 2 and 15 ppm of uranium as calcium uranate was passed through a magnetic separator containing stainless steel wool inclusions and shown in FIG.
磁気分離器の磁場は２０キロガウスであり、出力１５０
キロワツト、及び電磁石コイル直径は３０αである。The magnetic field of the magnetic separator is 20 kilogauss, and the output is 150
kilowatts, and the electromagnetic coil diameter is 30α.
この磁気分離器を毎時２トンのスラリか通過できろ。Can you pass 2 tons of slurry through this magnetic separator per hour?
磁気分離器中の介在物がウランを捕獲しなくなったこと
を螢光検出器か示した時、フッ化カルシウムの流れを止
め、介在物を１０％硝酸溶液で洗浄する。When the fluorescence detector indicates that the inclusions in the magnetic separator are no longer capturing uranium, the flow of calcium fluoride is stopped and the inclusions are washed with a 10% nitric acid solution.
次いで不肖酸中のウランはＤＥＰＡ−ＴＯＰＯ抽出剤を
使用して抽出する。The uranium in the unfavorable acid is then extracted using DEPA-TOPO extractant.
第１図は炭酸塩抽出器及びイオン交換カラムを使用した
ウラン回収方法を示すブロック図、第２図は硝酸洗浄器
を使用した他のウラン回収方法を示すブロック図である
。
図中、１・・・・・・分散剤、２・・・・・・配管、３
・・・・・・ボールミル、４・・・・・・ポンプ、５・
・・・・・サイクロン分離器、６・・・・・・リサイク
ル管、７・・・・・・配管、８・・・・・・バルブ、９
・・・・・・磁気分離器、１０・・・・・・鉄製容器、
１１，１２・・・・・・磁極、１３・・・・・・多孔質
高磁性介在物、１４・・・・・・検出器、１５・・・・
・・バルブ、１６・・・・・・スランジ脱水器、１８・
・・・・・配管、２１・・・・・・イオン交換カラム、
２２ 、２３・・・・・・ポンプ、３０・・・・・・配
管、３２・・・・・・磁気分離器、３３・・・・・・バ
ルブ、３５・・・・・・配管、３６・・・・・・バルブ
、３７・・・・・・磁気分離器、３８゜４０．４１．４
２，４３・・・・・・バルブ。FIG. 1 is a block diagram showing a uranium recovery method using a carbonate extractor and an ion exchange column, and FIG. 2 is a block diagram showing another uranium recovery method using a nitric acid scrubber. In the figure, 1...dispersant, 2...piping, 3
...Ball mill, 4...Pump, 5.
... Cyclone separator, 6 ... Recycle pipe, 7 ... Piping, 8 ... Valve, 9
...Magnetic separator, 10...Iron container,
11, 12... Magnetic pole, 13... Porous highly magnetic inclusion, 14... Detector, 15...
...Valve, 16...Slange dehydrator, 18.
... Piping, 21 ... Ion exchange column,
22, 23...Pump, 30...Piping, 32...Magnetic separator, 33...Valve, 35...Piping, 36 ... Valve, 37 ... Magnetic separator, 38゜40.41.4
2,43...Valve.
Claims (1)
ラリからウランを回収する方法において、該スラリを高
勾配磁気分離器に通し、次いで該分離器からウランを除
去する工程を含むことを特徴とする、ウランの回収方法
。1. A method for recovering uranium from an aqueous calcium fluoride slurry containing less than 1100 pI of iron, the method comprising the steps of passing the slurry through a high gradient magnetic separator and then removing the uranium from the separator. Collection method.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US26668181A | 1981-05-22 | 1981-05-22 | |
| US266681 | 1981-05-22 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57200224A JPS57200224A (en) | 1982-12-08 |
| JPS5930651B2 true JPS5930651B2 (en) | 1984-07-28 |
Family
ID=23015572
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57087187A Expired JPS5930651B2 (en) | 1981-05-22 | 1982-05-22 | How to recover uranium |
Country Status (7)
| Country | Link |
|---|---|
| EP (1) | EP0066419B1 (en) |
| JP (1) | JPS5930651B2 (en) |
| KR (1) | KR900000397B1 (en) |
| DE (1) | DE3272997D1 (en) |
| ES (1) | ES512466A0 (en) |
| YU (1) | YU106082A (en) |
| ZA (1) | ZA822690B (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4726895A (en) * | 1986-03-28 | 1988-02-23 | Edward Martinez | Process for concentration of gold and uranium magnetically |
| KR101322083B1 (en) * | 2007-05-30 | 2013-10-25 | 주식회사 케이씨씨 | A method for eliminating iron content from pyrophyllite |
| CN106890623B (en) * | 2017-03-09 | 2019-11-08 | 中国工程物理研究院核物理与化学研究所 | A kind of extraction of uranium from seawater adsorbent and preparation method thereof having anti-microbial property |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2965440A (en) * | 1957-01-11 | 1960-12-20 | Tripp Res Corp | Method of beneficiating uranium ores by forming ferromagnetic uranium values and magnetically separating same |
| US3394997A (en) * | 1965-04-12 | 1968-07-30 | Gen Electric | Method of preparing uranium diuranate |
| US3676337A (en) * | 1970-07-09 | 1972-07-11 | Massachusetts Inst Technology | Process for magnetic separation |
| GB1555670A (en) * | 1977-12-12 | 1979-11-14 | Atomic Energy Authority Uk | Magnetic separation of particles from liquids in a process for reprocessing nuclear fuel |
-
1982
- 1982-04-20 ZA ZA822690A patent/ZA822690B/en unknown
- 1982-05-18 YU YU01060/82A patent/YU106082A/en unknown
- 1982-05-20 EP EP82302567A patent/EP0066419B1/en not_active Expired
- 1982-05-20 DE DE8282302567T patent/DE3272997D1/en not_active Expired
- 1982-05-21 ES ES512466A patent/ES512466A0/en active Granted
- 1982-05-22 KR KR8202264A patent/KR900000397B1/en active
- 1982-05-22 JP JP57087187A patent/JPS5930651B2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| EP0066419B1 (en) | 1986-09-03 |
| DE3272997D1 (en) | 1986-10-09 |
| KR830010211A (en) | 1983-12-26 |
| EP0066419A3 (en) | 1983-11-02 |
| YU106082A (en) | 1985-03-20 |
| ES8403976A1 (en) | 1984-04-01 |
| KR900000397B1 (en) | 1990-01-25 |
| ES512466A0 (en) | 1984-04-01 |
| EP0066419A2 (en) | 1982-12-08 |
| JPS57200224A (en) | 1982-12-08 |
| ZA822690B (en) | 1983-06-29 |
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