JP2561909B2 - Treatment method of radioactive liquid waste - Google Patents
Treatment method of radioactive liquid wasteInfo
- Publication number
- JP2561909B2 JP2561909B2 JP60079317A JP7931785A JP2561909B2 JP 2561909 B2 JP2561909 B2 JP 2561909B2 JP 60079317 A JP60079317 A JP 60079317A JP 7931785 A JP7931785 A JP 7931785A JP 2561909 B2 JP2561909 B2 JP 2561909B2
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- JP
- Japan
- Prior art keywords
- fluorine
- calcium
- uranium
- nuclear fuel
- waste liquid
- 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 - Lifetime
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- Processing Of Solid Wastes (AREA)
- Removal Of Specific Substances (AREA)
- Separation Of Suspended Particles By Flocculating Agents (AREA)
Description
【発明の詳細な説明】 ［産業上の利用分野］ 本発明はフツ素及びウラン等の核燃料物質を含む放射
性廃液からフツ素及びウラン等の核燃料物質を同時に処
理し、除去する方法に関する。Description: TECHNICAL FIELD The present invention relates to a method for simultaneously treating and removing nuclear fuel substances such as fluorine and uranium from a radioactive liquid waste containing nuclear fuel substances such as fluorine and uranium.
［従来の技術］ 従来、放射性廃液の処理法として、ウラン、フツ素及
びアンモニアを含む廃液に溶存フツ素の当量以上のアル
カリ土類金属酸化物及びアルカリ土類金属水酸化物の１
種又は２種以上を添加し、ウランとフツ素を共沈除去す
る［含ウラン廃液の浄化法」が開示されている（特公昭
47−35199）。[Prior Art] Conventionally, as a method for treating radioactive waste liquid, 1 of an alkaline earth metal oxide and an alkaline earth metal hydroxide having an equivalent amount of dissolved fluorine or more to a waste liquid containing uranium, fluorine and ammonia is used.
A "purification method of uranium-containing waste liquid" in which uranium and fluorine are co-precipitated by adding one or more species is disclosed (Japanese Patent Publication No.
47-35199).
また、本出願人は別の放射性廃液の処理法として、ウ
ラン等の核燃料物質を含有するが、フツ素を含有しない
廃液に塩化鉄を添加し、完全に塩化鉄を溶解させた後、
圧縮空気を送り込みながらPHを調整してアルカリ性にす
ることにより、塩化鉄の沈殿とともにウラン等の核燃料
物質を凝集沈殿する「廃液中に浮遊するウラン酸化物微
粒子の除去方法」を特許出願した（特開昭56−12569
9）。Further, the present applicant has another method for treating radioactive waste liquid, which contains a nuclear fuel substance such as uranium, but after adding iron chloride to the waste liquid containing no fluorine and completely dissolving iron chloride,
A patent application was filed for "a method for removing fine particles of uranium oxide floating in the waste liquid" in which the pH of the uranium and other nuclear fuel materials is coagulated and precipitated by adjusting the pH to be alkaline while sending compressed air. Kaisho 56-12569
9).
更に、上記特公昭47−35199号公報に示される方法を
改良した方法として、ウランを含む溶液を加熱又は加熱
濃縮しながら水ガラス及びアルカリ土類金属塩を添加し
て沈殿物を生成し、この沈殿物を溶液から分離する「ウ
ランを含む廃液の処理方法」が提案されている（特開昭
59−20098）。Further, as a method improved from the method disclosed in JP-B-47-35199, water glass and an alkaline earth metal salt are added while heating or concentrating a solution containing uranium to form a precipitate. A "method for treating waste liquid containing uranium" for separating a precipitate from a solution has been proposed (Japanese Patent Laid-Open No. Sho 61-96).
59-20098).
［発明が解決しようとする課題］ 一般にフツ素及びウラン等の核燃料物質を含む放射性
廃液の処理法では、高い除染係数でフッ素及びウラン等
の核燃料物質を処理する必要がある。[Problems to be Solved by the Invention] Generally, in a method for treating a radioactive liquid waste containing a nuclear fuel substance such as fluorine and uranium, it is necessary to treat a nuclear fuel substance such as fluorine and uranium with a high decontamination coefficient.
しかし上記特公昭47−35199号公報に示される処理法
では、添加するアルカリ土類金属酸化物が酸化カルシウ
ムだけの場合には、上記公報の実施例１に示すように処
理前のウランの含有量が1.9mg/のところ、処理後のウ
ラン含有量は0.04mg/となるため、この例の除染係数
は22.5であり、高い除染係数でウランを除去することが
できない問題点があった。However, in the treatment method disclosed in JP-B-47-35199, when the alkaline earth metal oxide to be added is only calcium oxide, the content of uranium before treatment is as shown in Example 1 of the publication. However, since the uranium content after treatment is 0.04 mg /, the decontamination coefficient in this example is 22.5, and there is a problem that uranium cannot be removed with a high decontamination coefficient.
また上記特開昭56−125699号公報に示される処理法で
は、放射性廃液に塩化鉄を完全に溶解させて廃液中のウ
ラン等の核燃料物質を凝集沈殿させるために、廃液に比
較的多量の塩化鉄を添加する必要があり、しかも酸性に
変化した廃液にアルカリ溶液を添加してPH調整しなけれ
ばならない煩わしさがあった。またこの処理法では同時
にフツ素を除去できない不具合があった。Further, in the treatment method disclosed in the above-mentioned Japanese Patent Laid-Open No. 56-125699, a relatively large amount of chloride is added to the waste liquid in order to completely dissolve iron chloride in the radioactive waste liquid to coagulate and precipitate nuclear fuel substances such as uranium in the waste liquid. It was necessary to add iron, and the pH was adjusted by adding an alkaline solution to the acidified waste liquid. Further, this processing method has a problem that fluorine cannot be removed at the same time.
更に上記特開昭59−200998号公報に示される処理法で
は、上記特公昭47−35199号の処理法と同様にウランと
フツ素を同時に除去できるものの、処理液の加熱又は加
熱濃縮しながらアルカリ土類金属塩の他に水ガラスを添
加しなければならない。このためこの方法は多くの熱エ
ネルギとその後の処理が複雑となる水ガラスを必要とす
る欠点があった。Further, in the treatment method disclosed in JP-A-59-200998, although uranium and fluorine can be removed at the same time as in the treatment method of JP-B-47-35199, alkali is added while heating or concentrating the treatment solution. Water glass must be added in addition to the earth metal salts. Therefore, this method has a drawback that it requires a lot of heat energy and water glass which makes the subsequent processing complicated.
本発明の目的は、添加するアルカリ土類金属酸化物が
カルシウム化合物であっても比較的少量の塩化鉄を添加
することにより、放射性廃液中のフツ素及び放射性物質
を高い除染係数で除去することができる処理法を提供す
ることにある。An object of the present invention is to remove fluorine and radioactive substances in a radioactive liquid waste with a high decontamination coefficient by adding a relatively small amount of iron chloride even if the alkaline earth metal oxide to be added is a calcium compound. It is to provide a treatment method capable of processing.
本発明の別の目的は、塩化鉄を添加した後で廃液を十
分撹拌することにより、塩化鉄を廃液が酸性になるまで
添加し、その後アルカリ性にPH調整することなく、ウラ
ン等の核燃料物質を除去できる放射性廃液の処理法を提
供することにある。Another object of the present invention is to sufficiently stir the waste liquid after adding iron chloride, to add iron chloride until the waste liquid becomes acidic, and then to adjust the alkaline fuel to a nuclear fuel material such as uranium without adjusting the pH. An object of the present invention is to provide a method for treating radioactive waste liquid that can be removed.
本発明の更に別の目的は、単一の処理槽でフツ化物沈
殿とウランを捕集した水酸化第二鉄沈殿の固液分離を同
時に行い得る放射性廃液の処理法を提供することにあ
る。Still another object of the present invention is to provide a method for treating radioactive waste liquid capable of simultaneously performing solid-liquid separation of fluoride precipitation and ferric hydroxide precipitation in which uranium is collected in a single processing tank.
［課題を解決するための手段］ 本発明は、フツ素及び核燃料物質を含む放射性廃液に
前記廃液に溶存するフツ素の当量以上のアルカリ土類金
属酸化物、アルカリ土類金属水酸化物及びアルカリ土類
金属炭酸塩からなる群より選ばれた１種又は２種以上の
アルカリ土類金属化合物を添加してフツ素と核燃料物質
を共沈除去する放射性廃液の処理法の改良である。[Means for Solving the Problems] The present invention relates to a radioactive waste liquid containing fluorine and a nuclear fuel material, in which alkaline earth metal oxides, alkaline earth metal hydroxides and alkalis which are equal to or more than the equivalent amount of fluorine dissolved in the waste liquid are contained. It is an improvement of the method for treating radioactive waste liquid by adding one or more alkaline earth metal compounds selected from the group consisting of earth metal carbonates to coprecipitate fluorine and nuclear fuel substances.
その特徴ある構成は、アルカリ土類金属化合物が酸化
カルシウム、水酸化カルシウム及び炭酸カルシウムから
なる群より選ばれた１種又は２種以上のカルシウム化合
物であって、前記カルシウム化合物の添加後又は添加と
同時に前記廃液を撹拌しながら塩化鉄を更に添加するこ
とにより、アルカリ溶液を添加することなく前記フツ素
をフツ化物沈殿として固定するとともに前記核燃料物質
の一部をフツ化カルシウムの凝集沈殿にし、更に前記核
燃料物質の残部を水酸化第二鉄の凝集沈殿にし、前記フ
ツ化沈殿と前記フツ化カルシウム凝集沈殿と前記水酸化
第二鉄の凝集沈殿とを同時に固液分離することにある。Its characteristic constitution is that the alkaline earth metal compound is one or more calcium compounds selected from the group consisting of calcium oxide, calcium hydroxide and calcium carbonate, and after or after the addition of the calcium compound. At the same time, by further adding iron chloride while stirring the waste liquid, the fluorine is fixed as a fluoride precipitate without adding an alkaline solution, and a part of the nuclear fuel material is made into a flocculation precipitate of calcium fluoride, and further, The balance of the nuclear fuel material is the coagulation and precipitation of ferric hydroxide, and the fluorinated precipitation, the calcium fluorinated coagulation and the ferric hydroxide coagulation and precipitation are simultaneously subjected to solid-liquid separation.
即ち、本発明の処理法ではフツ素とウラン等の核燃料
物質を含む放射性廃液に酸化カルシウム、水酸化カルシ
ウム、炭酸カルシウム等のカルシウム化合物を添加し、
十分撹拌してフツ素とカルシウムの反応を進行させる。
これによりフツ素がフツ化カルシウム沈殿として固定さ
れるとともにウラン等の核燃料物質の一部をフツ化カル
シウムの凝集沈殿として処理する。この沈殿を濾過する
前に、更に少量の塩化鉄を添加し、十分撹拌して水酸化
第二鉄の凝集沈殿として残りのウラン等の核燃料物質を
沈殿させる。That is, in the treatment method of the present invention, calcium compounds such as calcium oxide, calcium hydroxide and calcium carbonate are added to radioactive waste liquid containing nuclear fuel substances such as fluorine and uranium,
Stir well to promote the reaction between fluorine and calcium.
As a result, fluorine is fixed as calcium fluoride precipitate, and at the same time, a part of the nuclear fuel material such as uranium is treated as calcium fluoride aggregate precipitate. Before filtering this precipitate, a small amount of iron chloride is further added and sufficiently stirred to precipitate the remaining nuclear fuel material such as uranium as a coagulating precipitate of ferric hydroxide.
本発明では、塩化鉄添加の際に廃液がアルカリ性であ
っても、前述した特開昭56−125699号公報の処理法と異
なり、塩化鉄を完全に溶解させるために廃液が酸性にな
るまで、塩化鉄を加える必要はない。この塩化鉄の添加
量は廃液に対して0.03重量％程度が好ましい。これより
少ないとウラン等の核燃料物質の凝集沈殿量が低く、ウ
ランを所定の排水基準値以下にすることができない。ま
たこれより多いと廃液が酸性に変化し、アルカリ溶液を
添加しなければならない煩わしさを生じる。In the present invention, even if the waste liquid is alkaline at the time of adding iron chloride, unlike the above-mentioned treatment method of JP-A-56-125699, until the waste liquid becomes acidic in order to completely dissolve iron chloride, It is not necessary to add iron chloride. The amount of iron chloride added is preferably about 0.03% by weight with respect to the waste liquid. If the amount is less than this, the amount of coagulation and sedimentation of nuclear fuel substances such as uranium is low, and it is not possible to bring uranium to below a prescribed standard value for wastewater. On the other hand, if the amount is larger than this, the waste liquid becomes acidic, which causes the troublesomeness of adding an alkaline solution.
本発明ではアルカリ土類金属のうち、カルシウムの酸
化物、水酸化物又は炭酸塩のようなカルシウム化合物が
使用されるが、作用効果及びコストと点で消石灰（Ca
（OH）２）が最も好適である。Among the alkaline earth metals, calcium compounds such as calcium oxide, hydroxide or carbonate are used in the present invention. However, slaked lime (Ca
(OH) 2 ) is most preferred.
本発明はカルシウム化合物と塩化鉄との添加によって
放射性廃液中のフツ素とウラン等の核燃料物質の処理を
１つの反応槽で同時に行うことができる。According to the present invention, the treatment of fluorine and nuclear fuel materials such as uranium in the radioactive waste liquid can be simultaneously performed in one reaction tank by adding the calcium compound and iron chloride.
次に本発明による処理結果について説明する。フツ素
及びウラン等核燃料物質を含む廃液に消石灰Ca（OH）２
及び塩化鉄を添加した場合のフツ素及びウランの除去効
果を第１表に示す。Next, the processing result according to the present invention will be described. Slaked lime Ca (OH) 2 in waste liquid containing nuclear fuel materials such as fluorine and uranium
Table 1 shows the effect of fluorine and uranium removal when iron and iron chloride were added.
第１表の＊印に示すNo.4の比較例ではPH＝３になるま
でFeCl3を加え、次にNaOHを加えてPH＝12とした場合で
ある。 In the comparative example of No. 4 shown by * in Table 1, FeCl 3 was added until PH = 3 and then NaOH was added to PH = 12.
第１表から、残存フツ素量に関しては、No.2及びNo.3
の本発明の実施例ではいずれも３〜5ppmに減少し、排水
規準値15ppm以下になつていることが判明した。フツ素
の除染係数はNo.2の実施例では約240であり、またNo.3
の実施例では約217であり、それぞれ高い値を示した。From Table 1, regarding residual fluorine content, No. 2 and No. 3
In all of the examples of the present invention, it was found that the amount decreased to 3 to 5 ppm and the drainage standard value became 15 ppm or less. The decontamination coefficient of fluorine is about 240 in the No. 2 example, and the No. 3
It was about 217 in each of the examples, and each showed a high value.
No.2の実施例では消石灰を添加した後、さらに塩化鉄
を添加し、水酸化第２鉄との凝集沈殿を生じせしめた場
合であるが、ウラン量は1.0×10-7μCi/ccと減少し、塩
化鉄添加効果によつてウラン溶液の排水規準値6.0×10
-7μCi/ccを満足していることを示し、かつウランの除
染係数は590であり、高い値を示している。またNo.2の
実施例では塩化鉄溶液を添加する前の廃液はPH＝13のア
ルカリ性であり、塩化鉄溶液添加と同時に水酸化第二鉄
の沈殿を生ずるが、塩化鉄を完全に溶解させて溶液を酸
性にしなくても、撹拌を十分に行えば該沈殿によるウラ
ン凝集効果のあることを示している。In the No. 2 example, after adding slaked lime and further adding iron chloride to cause coagulation and precipitation with ferric hydroxide, the amount of uranium is 1.0 × 10 −7 μCi / cc. The standard value of drainage of uranium solution is 6.0 × 10
-7 μCi / cc is satisfied, and the decontamination coefficient for uranium is 590, which is a high value. Further, in the No. 2 example, the waste liquid before the addition of the iron chloride solution was alkaline with PH = 13, and ferric hydroxide was precipitated simultaneously with the addition of the iron chloride solution, but the iron chloride was completely dissolved. It is shown that even if the solution is not made acidic by sufficient stirring, there is a uranium aggregating effect due to the precipitation if the stirring is sufficiently performed.
No.3の実施例は該廃液に消石灰と塩化鉄を同時に添加
した場合であるが、No.2の実施例の最終的な処理結果と
同等の効果を示している。即ち、No.3の実施例ではウラ
ン除染係数は220という高い値を示している。The example of No. 3 is a case where slaked lime and iron chloride are added to the waste liquid at the same time, and shows the same effect as the final treatment result of the example of No. 2. That is, in the No. 3 example, the uranium decontamination coefficient shows a high value of 220.
比較例のNo.4では、塩化鉄溶液を、塩化鉄が廃液中に
均一に溶解するような条件（PH＝３の酸性になるまで）
で添加し、その後該廃液のPHが12になるまで水酸化ナト
リウムを加え、水酸化第二鉄との凝集沈殿を生じせしめ
たところ、ウラン量は2.5×10-7μCi/ccに減少した。In No. 4 of the comparative example, the iron chloride solution was treated under conditions such that the iron chloride was uniformly dissolved in the waste liquid (until PH = 3, which was acidic).
After that, sodium hydroxide was added until the pH of the waste liquid became 12, and coagulation and precipitation with ferric hydroxide were caused. The amount of uranium was reduced to 2.5 × 10 −7 μCi / cc.
水酸化第二鉄沈殿によるウランの凝集効率はNo.2の実
施例及びNo.4の比較例のいずれの場合も10-7μCi/ccの
オーダでほぼ同等であるが、No.2の塩化鉄溶液添加量は
No.4のほぼ14％で効果があり、従つて廃棄物の減容効果
を考慮すると、No.2の実施例の方が望ましいことはもち
ろんである。The coagulation efficiency of uranium due to ferric hydroxide precipitation is almost the same in the order of 10 -7 μCi / cc in both the No. 2 example and the No. 4 comparative example, but the chlorination of No. 2 How much iron solution is added
It is effective in almost 14% of No. 4, and accordingly, considering the volume reduction effect of waste, it is needless to say that the No. 2 example is preferable.
本発明方法は以上の結果から、フツ素及びウラン等核
燃料物質を含む放射性廃液に消石灰と少量の塩化鉄溶液
を、溶液のPH調整なしに添加することができ、残存フツ
素量とウラン量とを排水基準値以下に減少せしめること
可能ならしめる方法であり、放射性廃液の処理上きわめ
て有用である。From the above results, the method of the present invention can add slaked lime and a small amount of iron chloride solution to a radioactive waste liquid containing a nuclear fuel material such as fluorine and uranium, without adjusting the pH of the solution, and the amount of residual fluorine and the amount of uranium. It is a method that can reduce the amount of wastewater to below the standard value of wastewater, and is extremely useful for the treatment of radioactive waste liquid.
次に、本発明を実施例によつてより具体的に説明する
が実施例は本発明の範囲を限定するものではない。Next, the present invention will be described more specifically by way of examples, but the examples do not limit the scope of the present invention.
フツ素721ppm,U濃度5.9×10-5μCi/ccを含むPH12の廃
液1200を入れた処理槽に含有フツ素量が全量反応して
CaF2を生成するとしたCa当量を少し上回るCa（OH）21.7
0kgを添加し、十分撹拌してCaF2の沈殿を生成させ、次
に、37.2wt％ FeCl3をこの廃液に１、即ち0.031重量
％添加し、Fe（OH）３の沈殿を生成させ、十分（30分以
上）に撹拌し、Fe（OH）３にウランを捕集させる。かく
て、生成したCaF2とFe（OH）３の殿物を同時に固液分離
することにより、フツ素とウラン濃度とも排水規準値以
下に処理することができた。除染係数はフツ素が約240
であり、ウランが590であり、それぞれ高い値を示し
た。Fluorine 721ppm, U concentration 5.9 × 10 -5 μCi / cc PH12 waste liquid 1200 was put into the treatment tank and the total amount of fluorine contained reacted.
Ca (OH) 2 1.7, which is slightly higher than the Ca equivalent used to generate CaF 2.
Add 0 kg and stir well to produce a CaF 2 precipitate, then add 37.2 wt% FeCl 3 to this effluent 1, ie 0.031 wt%, to produce a Fe (OH) 3 precipitate, Stir (30 minutes or more) to collect uranium on Fe (OH) 3 . Thus, by simultaneously performing solid-liquid separation of the produced CaF 2 and Fe (OH) 3 precipitates, both the fluorine and uranium concentrations could be treated below the drainage standard value. Decontamination factor is about 240 for fluorine
And uranium was 590, which were high values.
本発明は上記の構成をとることによつて、次の効果を
示すものである。The present invention has the following effects due to the above configuration.
（１） フツ素及びウラン等の核燃料物質を含む放射性
廃液に対してカルシウム化合物と少量の塩化鉄を加える
と、残存フツ素量のみでなく、残存ウラン等核燃料物質
をも排水規準値以下に減少させることができ、かつ高い
除染係数で処理することができる。(1) When a calcium compound and a small amount of iron chloride are added to a radioactive liquid waste containing nuclear fuel substances such as fluorine and uranium, not only the amount of residual fluorine but also the amount of residual uranium and other nuclear fuel substances is reduced to below the drainage standard value. And can be treated with a high decontamination coefficient.
（２） 塩化鉄添加時の該廃液がアルカリ性であると、
添加と同時に水酸化第二鉄の沈殿を生ずるが、該廃液を
十分撹拌することにより、この沈殿によるウラン等核燃
料物質の捕集効果を十分に達成させることができる。(2) If the waste liquid at the time of adding iron chloride is alkaline,
Precipitation of ferric hydroxide occurs at the same time as the addition, but by sufficiently stirring the waste liquid, the effect of collecting nuclear fuel substances such as uranium by this precipitation can be sufficiently achieved.
（３） 上記（２）で述べたことは、塩化鉄を溶液中に
均一に溶解せしめる溶解条件は、一旦PH調整した後、塩
化鉄を加え溶解させ、さらにアルカリ性物質を加えて水
酸化第二鉄の沈殿に変化させる操作を、本発明は必要と
しないことを示すもので該放射性廃液処理工程を簡略化
することができる。(3) As described in (2) above, the dissolution conditions for uniformly dissolving iron chloride in the solution are that pH is adjusted once, iron chloride is added and dissolved, and then an alkaline substance is added to the second hydroxide. The present invention does not require the operation of changing to the precipitation of iron, and thus the radioactive waste liquid treatment step can be simplified.
（４） 本発明のフツ化物沈殿とウランを捕集した水酸
化第二鉄沈殿の固液分離を同時に、かつ１つの処理槽内
で行うことが可能であるので、簡単な処理装置で済み、
その経済的効果は大きい。(4) Since it is possible to perform the solid-liquid separation of the fluoride precipitate of the present invention and the ferric hydroxide precipitate collecting uranium at the same time and in one processing tank, a simple processing device is sufficient.
Its economic effect is great.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 亀井 義信 茨城県那珂郡東海村大字舟石川622番地 １ 三菱原子燃料株式会社東海製作所内 (56)参考文献 特開 昭59−200998（ＪＰ，Ａ) 特開 昭56−125699（ＪＰ，Ａ) 特公 昭47−35199（ＪＰ，Ｂ２) ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Yoshinobu Kamei, 622, Funaishikawa, Tokai-mura, Naka-gun, Ibaraki Prefecture 1 Mitsubishi Nuclear Fuel Co., Ltd. Tokai Works (56) Reference JP-A-59-200998 (JP, A) JP 56-125699 (JP, A) JP 47-35199 (JP, B2)
Claims (1)
前記廃液に溶存するフツ素の当量以上のアルカリ土類金
属酸化物、アルカリ土類金属水酸化物及びアルカリ土類
金属炭酸塩からなる群より選ばれた１種または２種以上
のアルカリ土類金属化合物を添加してフツ素と核燃料物
質を共沈除去する放射性廃液の処理法において、 前記アルカリ土類金属化合物は酸化カルシウム、水酸化
カルシウム及び炭酸カルシウムからなる群より選ばれた
１種又は２種以上のカルシウム化合物であって、前記カ
ルシウム化合物の添加後又は添加と同時に前記廃液を撹
拌しながら塩化鉄を添加することにより、アルカリ溶液
を添加することなく前記フツ素をフツ化物沈殿として固
定するとともに前記核燃料物質の一部をフツ化カルシウ
ムの凝集沈殿にし、更に前記核燃料物質の残部を水酸化
第二鉄の凝集沈殿にし、 前記フツ化物沈殿と前記フツ化カルシウム凝集沈殿と前
記水酸化第二鉄の凝集沈殿とを同時に固液分離する ことを特徴とする放射性廃液の処理法。1. A group consisting of an alkaline earth metal oxide, an alkaline earth metal hydroxide, and an alkaline earth metal carbonate in a radioactive liquid waste containing fluorine and a nuclear fuel material in an amount equal to or more than the amount of fluorine dissolved in the liquid waste. In the method for treating a radioactive liquid waste, in which fluorine and nuclear fuel substances are coprecipitated by adding one or more alkaline earth metal compounds selected from the above, the alkaline earth metal compound is calcium oxide or calcium hydroxide. And one or more calcium compounds selected from the group consisting of calcium carbonate, and by adding iron chloride while stirring the waste liquid after or at the same time as adding the calcium compound, an alkaline solution is obtained. The fluorine is fixed as a fluoride precipitate without addition and a part of the nuclear fuel material is aggregated and precipitated with calcium fluoride. The balance of the nuclear fuel material is ferric hydroxide coagulation-precipitation, and the fluoride precipitation, the calcium fluoride coagulation-precipitation, and the ferric hydroxide coagulation-precipitation are simultaneously subjected to solid-liquid separation. Waste liquid treatment method.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60079317A JP2561909B2 (en) | 1985-04-16 | 1985-04-16 | Treatment method of radioactive liquid waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60079317A JP2561909B2 (en) | 1985-04-16 | 1985-04-16 | Treatment method of radioactive liquid waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61239196A JPS61239196A (en) | 1986-10-24 |
| JP2561909B2 true JP2561909B2 (en) | 1996-12-11 |
Family
ID=13686490
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60079317A Expired - Lifetime JP2561909B2 (en) | 1985-04-16 | 1985-04-16 | Treatment method of radioactive liquid waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2561909B2 (en) |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56125699A (en) * | 1980-03-07 | 1981-10-02 | Mitsubishi Genshi Nenryo Kk | Method of removing uranium oxide particles floating in waste liquid |
| JPS59200998A (en) * | 1983-04-28 | 1984-11-14 | 三菱重工業株式会社 | Method of processing liquid waste containing uranium |
-
1985
- 1985-04-16 JP JP60079317A patent/JP2561909B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61239196A (en) | 1986-10-24 |
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