JPH1194993A - Method for treating radioactive material containing waste liquid - Google Patents

Method for treating radioactive material containing waste liquid

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Publication number
JPH1194993A
JPH1194993A JP9274987A JP27498797A JPH1194993A JP H1194993 A JPH1194993 A JP H1194993A JP 9274987 A JP9274987 A JP 9274987A JP 27498797 A JP27498797 A JP 27498797A JP H1194993 A JPH1194993 A JP H1194993A
Authority
JP
Japan
Prior art keywords
waste liquid
containing waste
radioactive substance
radioactive
solution
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.)
Withdrawn
Application number
JP9274987A
Other languages
Japanese (ja)
Inventor
Tatae Matsumoto
湛 松本
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nuclear Fuel Industries Ltd
Original Assignee
Nuclear Fuel Industries Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Nuclear Fuel Industries Ltd filed Critical Nuclear Fuel Industries Ltd
Priority to JP9274987A priority Critical patent/JPH1194993A/en
Publication of JPH1194993A publication Critical patent/JPH1194993A/en
Withdrawn legal-status Critical Current

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Abstract

PROBLEM TO BE SOLVED: To propose a method for treating radioactive material containing waste liquid capable of completely removing radioactive materials in radioactive material containing waste liquid. SOLUTION: In this method, radioactive material containing waste liquid added with ferric chloride FeCl3 is neutralized with alkali to produce ferric hydroxide Fe(OH)3 and the radioactive materials taken in this ferric hydroxide Fe(OH)3 is filtered to remove together with this ferric hydroxide. At this moment before ferric hydroxide Fe(OH)3 is produced in the waste liquid, tannic acid is added in advance to make the radioactive material complex.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は、ウラン元素又は、
プルトニウム元素やアメリシウム元素などの超ウラン元
素を含む放射性物質含有廃液の処理方法に関するもので
ある。
[0001] The present invention relates to a uranium element or
The present invention relates to a method for treating a radioactive substance-containing waste liquid containing a transuranium element such as a plutonium element or an americium element.

【0002】[0002]

【従来の技術】従来より、ウラン元素又は、プルトニウ
ム元素やアメリシウム元素などの超ウラン元素(以後、
単に放射性物質と称す)を含む放射性物質含有廃液を処
理するために、Fe(OH)3 による共沈を利用した方法が採
用されている。
2. Description of the Related Art Conventionally, a uranium element or a transuranium element such as a plutonium element or an americium element (hereinafter referred to as a "uranium element") has been known.
A method utilizing co-precipitation with Fe (OH) 3 has been adopted to treat a radioactive substance-containing waste liquid containing a radioactive substance.

【0003】この方法は、大体以下の手順で行われる。
まず、放射性物質含有廃液に塩化第二鉄(FeCl3) 液を添
加してよく撹拌した後、水酸化ナトリウム(NaOH)液等の
アルカリを加えて中和することにより、塩化第二鉄(FeC
l3) を以下の式のように反応させて水酸化鉄Fe(OH)3
する。
This method is generally performed in the following procedure.
First, a ferric chloride (FeCl 3 ) solution is added to a radioactive substance-containing waste liquid, and the mixture is stirred well.Then, an alkali such as sodium hydroxide (NaOH) is added to neutralize the ferric chloride (FeC 3).
l 3 ) is reacted as in the following formula to obtain iron hydroxide Fe (OH) 3 .

【0004】FeCl3 + 3NaOh → 3Fe(OH)3 + 3NaCl[0004] FeCl 3 + 3NaOh → 3Fe (OH) 3 + 3NaCl

【0005】廃液中に生成したFe(OH)3 はフロック状の
物質であり、廃液中の不純物を吸着などにより取り込ん
で沈殿(共沈)するため、廃液中の放射性物質は、この
ときFe(OH)3 と共に沈殿する。
[0005] The Fe (OH) 3 generated in the waste liquid is a floc-like substance, and the impurities in the waste liquid are taken up by adsorption or the like and precipitated (coprecipitation). Precipitates with (OH) 3 .

【0006】水酸化ナトリウム(NaOH)液による中和後、
廃液を濾過して廃液中に生成された沈殿物を取り除くこ
とで、沈殿物とともに放射性物質を廃液中から取り除
く。
After neutralization with sodium hydroxide (NaOH) solution,
By filtering the waste liquid and removing the precipitate generated in the waste liquid, the radioactive substance is removed from the waste liquid together with the precipitate.

【0007】[0007]

【発明が解決しようとする課題】しかしながら、放射性
物質はFe(OH)3 に比べて非常に微小なものであるため、
上述の方法ではFe(OH)3 による完全な取り込みが難しい
という難点がある。
However, since radioactive materials are very small compared to Fe (OH) 3 ,
The above method has a disadvantage that it is difficult to completely incorporate Fe (OH) 3 .

【0008】そのため、場合によっては廃液中の放射性
物質含有量が基準値以下になるまで何度も上述した廃液
処理を繰り返せねばならず、その分、コストと手間がか
かるだけでなく、二次沈殿物が大量となり、放射性廃棄
物の保管スペース及びコストが増大するので好ましくな
い。
[0008] Therefore, in some cases, the above-mentioned waste liquid treatment must be repeated many times until the radioactive substance content in the waste liquid becomes equal to or less than the reference value, which not only requires cost and labor, but also causes secondary precipitation. This is not preferable because a large amount of material is required, and the storage space and cost for radioactive waste increase.

【0009】そこで本発明では、放射性物質含有廃液中
の放射能物質を完全に取り除くことのできる放射性物質
含有廃液の処理方法を提案することを主目的としてい
る。また、放射性物質の含有量が極微量であっても完全
に取り除くことのできる放射性物質含有廃液の処理方法
を提案することも本発明の別の目的である。
Accordingly, an object of the present invention is to propose a method for treating a radioactive substance-containing waste liquid that can completely remove a radioactive substance from the radioactive substance-containing waste liquid. It is another object of the present invention to propose a method for treating a radioactive substance-containing waste liquid which can be completely removed even if the content of the radioactive substance is extremely small.

【0010】[0010]

【課題を解決するための手段】上記の目的を達成するた
め、請求項1に係る発明は、塩化第二鉄FeCl3 を添加し
た放射性物質含有廃液をアルカリにより中和して水酸化
鉄Fe(OH)3 を生成したのち、濾過することにより水酸化
鉄Fe(OH)3 と共に該水酸化鉄Fe(OH)3 に取り込まれた放
射性物質を除去する放射性物質含有廃液の処理方法にお
いて、前記廃液に予めタンニン酸を添加することを特徴
としている。
Means for Solving the Problems To achieve the above object, the invention according to claim 1 is to neutralize a waste liquid containing a radioactive substance to which ferric chloride (FeCl 3) is added with an alkali to obtain an iron hydroxide (Fe). OH) 3 After generating the, in the processing method of the radioactive substance-containing waste liquid to remove radioactive material taken into the aqueous iron oxide Fe (OH) 3 with iron hydroxide Fe (OH) 3 by filtration, the waste liquid Is characterized by adding tannic acid in advance.

【0011】即ち、請求項1の発明では、タンニン酸
が、ウラン元素又はプルトニウム元素やアメリシウム元
素などの超ウラン元素などの放射性物質と結合して複合
体となることに着目して、廃液中に水酸化鉄Fe(OH)3
生成させる前に、予め放射性物質をタンニン酸により複
合体化させておくことで分子としての寸法を大きくして
おき、これにより水酸化鉄Fe(OH)3 による放射性物質の
取り込みを容易にしている。尚、この際に過剰のタンニ
ンとFeとが反応してタンニン−鉄化合物が一部生成し、
これもフロック状の物質であるので放射性物質の取り込
みに寄与しているものと考えられる。
That is, in the first aspect of the present invention, attention is paid to the fact that tannic acid combines with a radioactive substance such as uranium element or transuranium element such as plutonium element or americium element to form a complex, and the tannic acid is contained in the waste liquid. Before producing iron hydroxide Fe (OH) 3 , the size as a molecule is increased by previously forming a radioactive substance into a complex with tannic acid, and thereby the iron hydroxide Fe (OH) 3 It facilitates the uptake of radioactive materials. In this case, excess tannin and Fe react with each other to form a tannin-iron compound,
Since this is also a floc-like substance, it is considered to have contributed to the incorporation of radioactive substances.

【0012】また、請求項2の発明は、請求項1に記載
の放射性物質含有廃液の処理方法において、タンニン酸
を添加した後、一定時間撹拌してから塩化第二鉄FeCl3
を添加し、アルカリ中和することを特徴としている。
According to a second aspect of the present invention, in the method for treating a radioactive substance-containing waste liquid according to the first aspect, after adding tannic acid, the mixture is stirred for a certain period of time, and then the ferric chloride FeCl 3 is added.
And neutralizing with alkali.

【0013】即ち、請求項2の発明では、タンニン酸を
添加したのちに、一定時間撹拌することにより放射性物
質のタンニン酸による複合体化の効率を向上させて水酸
化鉄Fe(OH)3 による放射性物質の取り込みをより確実に
している。
According to the second aspect of the present invention, after adding tannic acid, the mixture is stirred for a certain period of time to improve the efficiency of complexation of the radioactive substance with tannic acid, thereby increasing the efficiency of the iron hydroxide Fe (OH) 3 . It ensures the uptake of radioactive materials.

【0014】[0014]

【発明の実施の形態】以後、本発明について実施例を用
いて更に詳細に説明する。まず、U3O8をU含有量が約10
ppmとなるように硝酸に溶解して不純物を全く含まない
放射性物質含有液を作成し、標準液とした。この標準液
の放射線量を測定したところ、6.872× 102 mmBq/ccで
あった。また、日常検査業務での分析で発生した雑廃液
をpH7に調整して濾過し、雑多な不純物を含有する放射
性物質含有液を作成し、試験液とした。この試験液の放
射線量を測定したところ、4.890 × 102 mmBq/ccであっ
た。
DESCRIPTION OF THE PREFERRED EMBODIMENTS Hereinafter, the present invention will be described in more detail with reference to embodiments. First, U 3 O 8 has a U content of about 10
A radioactive substance-containing solution containing no impurities at all by dissolving in nitric acid so as to be ppm was prepared and used as a standard solution. When the radiation dose of this standard solution was measured, it was 6.873 × 10 2 mmBq / cc. In addition, the miscellaneous waste liquid generated in the analysis in the daily inspection work was adjusted to pH 7 and filtered to prepare a radioactive substance-containing liquid containing miscellaneous impurities, which was used as a test liquid. When the radiation dose of this test solution was measured, it was 4.890 × 10 2 mmBq / cc.

【0015】まず、本発明の実施例として、上記標準液
100 ccにタンニン酸 0.5gを加えて1時間撹拌後、塩化
第二鉄FeCl3 を4g添加したものをNo.1液、上記試験液
100ccにタンニン酸 0.5gを加えて1時間撹拌後、塩化
第二鉄FeCl3 を4g添加したものをNo.3液とし、それぞ
れ水酸化ナトリウムNaOH水溶液によりpH5に調整した
後、濾過した。処理の終了した廃液の放射線量を測定
し、この値からウランの除去率を計算したところ、No.1
液は98.7%、No.3液は99.5%であった。
First, as an embodiment of the present invention, the standard solution
After adding 0.5 g of tannic acid to 100 cc and stirring for 1 hour, add 4 g of ferric chloride FeCl 3 to the No. 1 solution, the above test solution.
After adding 0.5 g of tannic acid to 100 cc and stirring for 1 hour, a solution to which 4 g of ferric chloride FeCl 3 was added was used as a No. 3 solution, and each was adjusted to pH 5 with an aqueous solution of sodium hydroxide and then filtered. When the radiation dose of the waste liquid after treatment was measured and the uranium removal rate was calculated from this value, it was No. 1
The liquid was 98.7% and the No. 3 liquid was 99.5%.

【0016】又、No.1液とNo.3液とをそれぞれ水酸化ナ
トリウムNaOH水溶液によりpH 7.5に調整した後、濾過し
た。処理の終了した廃液の放射線量を測定し、この値か
らウランの除去率を計算したところ、No.1液は 100%、
No.3液も 100%であった。
The No. 1 solution and the No. 3 solution were each adjusted to pH 7.5 with an aqueous solution of sodium hydroxide and filtered. The radiation dose of the waste liquid after the treatment was measured and the uranium removal rate was calculated from this value.
No. 3 solution was also 100%.

【0017】このことから、廃液中のウランをタンニン
酸により完全に複合化した状態で中和(即ち、pH7前後
に調整)すれば、完全に水酸化鉄Fe(OH)3 による放射性
物質の取り込みが行われることがわかった。
From this fact, if the uranium in the waste liquid is neutralized (that is, adjusted to a pH of about 7) in a state of being completely complexed with tannic acid, the incorporation of radioactive substances by the iron hydroxide Fe (OH) 3 completely Turned out to be done.

【0018】比較例として上記標準液100 ccに対して塩
化第二鉄FeCl3 を4g添加したものをNo.2液、また、上
記試験液100 ccに対して塩化第二鉄FeCl3 を4g添加し
たものをNo.4液とし、それぞれ水酸化ナトリウムNaOH水
溶液によりpH5に調整したのち、濾過した。処理の終了
した廃液の放射線量を測定し、この値からウランの除去
率を計算したところ、No.2液は99.5%、No.4液は98.2%
であった。
[0018] No.2 solution which ferric FeCl 3 chloride was added 4g against the standard liquid 100 cc as a comparative example, also, the ferric FeCl 3 chloride 4g added to the test solution 100 cc The resulting solution was used as a No. 4 solution, adjusted to pH 5 with an aqueous solution of sodium hydroxide and then filtered. The radiation dose of the waste liquid after treatment was measured, and the uranium removal rate was calculated from this value. The No. 2 liquid was 99.5% and the No. 4 liquid was 98.2%.
Met.

【0019】又、No.2液とNo.4液とをそれぞれ水酸化ナ
トリウムNaOH水溶液によりpH 7.5に調整した後、濾過し
た。処理の終了した廃液の放射線量を測定し、この値か
らウランの除去率を計算したところ、No.2液は99.6%、
No.4液は97.2%であった。
The No. 2 solution and the No. 4 solution were each adjusted to pH 7.5 with an aqueous solution of sodium hydroxide and filtered. The radiation dose of the waste liquid after the treatment was measured, and the uranium removal rate was calculated from this value.
No. 4 solution was 97.2%.

【0020】即ち、タンニン酸を添加しない場合も比較
的高いウラン除去率を示すが、本発明の実施例のように
100%の除去率は得られていないことがわかる。尚、
以上に述べた実施例ではウラン含有標準液について除去
効果を示したが、本発明の方法はウラン元素はもちろ
ん、プルトニウムやアメリシウムなどの他の超ウラン元
素を含む各種の放射性物質含有廃液に対して有効であ
り、また前記標準液だけでなく分析使用済み廃液や工程
廃水のような有機物をはじめとする種々の不純物を含む
放射性物質含有廃液に対しても放射性物質の除去に顕著
な効果を示すことが確認されている。
That is, even when tannic acid was not added, a relatively high uranium removal rate was exhibited, but it was found that a 100% removal rate was not obtained as in the examples of the present invention. still,
In the examples described above, the removal effect was shown for the uranium-containing standard solution, but the method of the present invention is applicable to various radioactive substance-containing waste liquids containing not only uranium elements but also other transuranium elements such as plutonium and americium. It is effective, and has a remarkable effect on the removal of radioactive substances not only for the standard solution but also for radioactive substance-containing waste liquids containing various impurities including organic substances such as analytically used waste liquids and process wastewaters. Has been confirmed.

【0021】[0021]

【発明の効果】このように、本発明では、放射性物質含
有廃液中の放射能物質を、特に、放射性物質含有量が極
微量であっても完全に取り除くことができる。そのた
め、廃液中の放射性物質含有量が基準値以下になるまで
何度も処理することがないので、コスト面と作業効率の
点で好ましく、二次沈殿物の量も最小限に抑えることが
できる。また、本発明の放射性物質含有廃液の処理方法
は、従来の方法で用いた設備を流用することができるの
で、設備投資など新たな出費が少なくて済むという好ま
しい利点がある。
As described above, according to the present invention, the radioactive substance in the radioactive substance-containing waste liquid can be completely removed, even if the radioactive substance content is extremely small. Therefore, since the radioactive material content in the waste liquid is not repeatedly processed until it becomes equal to or less than the reference value, it is preferable in terms of cost and work efficiency, and the amount of the secondary precipitate can be minimized. . Further, the method for treating a radioactive substance-containing waste liquid of the present invention has a preferable advantage that new equipment and other new expenses can be reduced because equipment used in the conventional method can be used.

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】 塩化第二鉄FeCl3 を添加した放射性物質
含有廃液をアルカリにより中和して水酸化鉄Fe(OH)3
生成したのち、濾過することにより水酸化鉄Fe(OH)3
共に該水酸化鉄Fe(OH)3 に取り込まれた放射性物質を除
去する放射性物質含有廃液の処理方法において、 前記廃液に予めタンニン酸を添加することを特徴とする
放射性物質含有廃液の処理方法。
1. A radioactive substance-containing waste liquid to which ferric chloride FeCl 3 has been added is neutralized with alkali to produce iron hydroxide Fe (OH) 3 , and then filtered to obtain iron hydroxide Fe (OH) 3. A method for treating a radioactive substance-containing waste liquid for removing radioactive substances taken into the iron hydroxide Fe (OH) 3 , wherein tannic acid is added to the waste liquid in advance.
【請求項2】 タンニン酸を添加した後、一定時間撹拌
してから塩化第二鉄FeCl3 を添加し、アルカリ中和する
ことを特徴とする請求項1に記載の放射性物質含有廃液
の処理方法。
2. The method for treating a radioactive substance-containing waste liquid according to claim 1, wherein after adding tannic acid, the mixture is stirred for a predetermined time, and then ferric chloride FeCl 3 is added to neutralize the alkali. .
JP9274987A 1997-09-24 1997-09-24 Method for treating radioactive material containing waste liquid Withdrawn JPH1194993A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP9274987A JPH1194993A (en) 1997-09-24 1997-09-24 Method for treating radioactive material containing waste liquid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP9274987A JPH1194993A (en) 1997-09-24 1997-09-24 Method for treating radioactive material containing waste liquid

Publications (1)

Publication Number Publication Date
JPH1194993A true JPH1194993A (en) 1999-04-09

Family

ID=17549337

Family Applications (1)

Application Number Title Priority Date Filing Date
JP9274987A Withdrawn JPH1194993A (en) 1997-09-24 1997-09-24 Method for treating radioactive material containing waste liquid

Country Status (1)

Country Link
JP (1) JPH1194993A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002172395A (en) * 2000-12-05 2002-06-18 Nec Environment Eng Ltd Method for iron hydroxide flocculation and sedimentation treatment of thick inorganic component- containing wastewater
KR100485973B1 (en) * 2002-11-20 2005-05-03 주식회사 데콘엔지니어링 A preliminary acid cleansing device of a high radioactive contamination metal
JP2013122010A (en) * 2011-12-12 2013-06-20 Mitsuya Tanimoto Treating agent for countermeasure of contaminated soil, and treatment method
CN114249450A (en) * 2020-09-21 2022-03-29 西南科技大学 Method for one-step deep purification of high-concentration organic uranium-containing low-level radioactive waste liquid by using magnetic ferrite

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2002172395A (en) * 2000-12-05 2002-06-18 Nec Environment Eng Ltd Method for iron hydroxide flocculation and sedimentation treatment of thick inorganic component- containing wastewater
KR100485973B1 (en) * 2002-11-20 2005-05-03 주식회사 데콘엔지니어링 A preliminary acid cleansing device of a high radioactive contamination metal
JP2013122010A (en) * 2011-12-12 2013-06-20 Mitsuya Tanimoto Treating agent for countermeasure of contaminated soil, and treatment method
CN114249450A (en) * 2020-09-21 2022-03-29 西南科技大学 Method for one-step deep purification of high-concentration organic uranium-containing low-level radioactive waste liquid by using magnetic ferrite

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Effective date: 20041207