JPS6055800B2 - How to recover plutonium from a solution containing plutonium - Google Patents

How to recover plutonium from a solution containing plutonium

Info

Publication number
JPS6055800B2
JPS6055800B2 JP55113200A JP11320080A JPS6055800B2 JP S6055800 B2 JPS6055800 B2 JP S6055800B2 JP 55113200 A JP55113200 A JP 55113200A JP 11320080 A JP11320080 A JP 11320080A JP S6055800 B2 JPS6055800 B2 JP S6055800B2
Authority
JP
Japan
Prior art keywords
plutonium
solution containing
recover
solution
present
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
Application number
JP55113200A
Other languages
Japanese (ja)
Other versions
JPS5737292A (en
Inventor
胤昭 矢幡
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.)
Japan Atomic Energy Agency
Original Assignee
Japan Atomic Energy Research Institute
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 Japan Atomic Energy Research Institute filed Critical Japan Atomic Energy Research Institute
Priority to JP55113200A priority Critical patent/JPS6055800B2/en
Publication of JPS5737292A publication Critical patent/JPS5737292A/en
Publication of JPS6055800B2 publication Critical patent/JPS6055800B2/en
Expired legal-status Critical Current

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

  • Manufacture And Refinement Of Metals (AREA)

Description

【発明の詳細な説明】 本発明はプルトニウムを含む溶液からプルトニウムを回
収する方法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for recovering plutonium from a solution containing plutonium.

より詳細に述べると、本発明は低濃度のＰｕを含有する
溶液に特定の可溶性のフッ化物を添加してＰｕを回収す
る方法に関する。Ｐｕ化合物中のＰｕを化学分析するに
は通常電位差滴定法が用いられている。More specifically, the present invention relates to a method for recovering Pu by adding a specific soluble fluoride to a solution containing a low concentration of Pu. Potentiometric titration is usually used to chemically analyze Pu in Pu compounds.

Ｐυ（ＩＶ）は酸性溶液中で〜、Ｆｅ、Ｃｒ等のイオン
と共存している。Ｐｕ化合物中の Ｐｕ化学分析例とし
ては、Ｕ−Ｐｕ混合酸化物またはＵ−Ｐｕ混合炭化物中
のＵとＰｕの割合を調べる場所が最も多いため、化学分
析後の溶液には上記金属イオンの他にＵＮＶ）Ｍｏ等が
含まれている。これらの化学分析の結果生じた溶液（廃
液）中のＰｕ（ＩＶ）濃度はＯ、１９ｙ／ｌ以下の場合
が多い。この様な低濃度のＰｕを回収することは極めて
困難なため溶液のまま一時保管するか中和した後固体化
して廃棄物とせざるを得ないのが実状である。従つて、
低濃度のＰｕを含む溶液からＰｕを効率よく回収する方
法の確立が望まれていた。Pυ(IV) coexists with ions such as ~, Fe, and Cr in an acidic solution. As an example of chemical analysis of Pu in Pu compounds, the ratio of U and Pu in U-Pu mixed oxides or U-Pu mixed carbides is most commonly investigated, so the solution after chemical analysis contains other than the above metal ions. contains UNV) Mo, etc. The Pu(IV) concentration in the solution (waste liquid) produced as a result of these chemical analyzes is often less than 0.19y/l. Since it is extremely difficult to recover Pu at such a low concentration, the actual situation is that it must be temporarily stored as a solution or solidified after neutralization and disposed of as waste. Therefore,
It has been desired to establish a method for efficiently recovering Pu from solutions containing low concentrations of Pu.

本発明はＰｕ（ＩＶ）がＮＨ、ＦまたはＮＨ、Ｆ−ＨＦ
等可溶性のフッ化物と反応して溶解度の低い錯化合物を
形成して沈殿させる一方Ｐｕ（ＩＶ）と共存する〜、Ｆ
ｅ等はフッ化物の溶解度が大きいものまたは錯イオンを
生成するものてあるために沈殿を生成しないことに着目
した。In the present invention, Pu(IV) is NH, F or NH, F-HF.
F
We focused on the fact that e.g. does not form a precipitate because it has a high solubility of fluoride or forms a complex ion.

従つて、この反応を利用することによつて、Ｐｕ（ＩＶ
）のみがフッ化物として分離回収出来る。Therefore, by utilizing this reaction, Pu(IV
) can be separated and recovered as fluoride.

但し、Ｐｕ（ＩＶ）とＡｍなどの超プルトニウム元素の
イオンが共存する場合はプルトニウムと共沈する。However, when Pu(IV) and ions of super plutonium elements such as Am co-exist, they co-precipitate with plutonium.

本発明で使用されるフッ化物としては可溶性のＮＨ４Ｆ
、、ＮＨ４Ｆ−ＨＦ）ＫＦ）ＨＦ）Ｎｏ、Ｆ等が例示さ
れるが、実効価値のあるものとしてはＮＨ、ＦおよびＮ
Ｈ、Ｆ−ＨＦ等可溶性の粉末状フッ化物が特に望ましい
。The fluoride used in the present invention is soluble NH4F.
, NH4F-HF)KF)HF)No, F, etc., but those with effective value include NH, F and N.
Particularly desirable are soluble powdered fluorides such as H and F-HF.

以上本発明を実施例により説明する。The present invention will be described above with reference to Examples.

８０％Ｕ−２０％Ｐｕ混合酸化物をＨＮＯ３に溶解した
後、各々を電位差滴定法て分析した後生じた廃液３ｅを
試料として用いた。After dissolving the 80% U-20% Pu mixed oxide in HNO3, each was analyzed by potentiometric titration, and the resulting waste liquid 3e was used as a sample.

Claims (1)

【特許請求の範囲】[Claims] １ プルトニウムを含む水溶液にＮＨ＿４ＦおよびＮＨ
＿４Ｆ・ＨＦから成る群から選択される可溶性フッ化物
を添加してプルトニウムを錯化合物として沈殿させて回
収する方法。1 NH_4F and NH in an aqueous solution containing plutonium
A method of collecting plutonium by precipitating it as a complex compound by adding a soluble fluoride selected from the group consisting of _4F and HF.
JP55113200A 1980-08-18 1980-08-18 How to recover plutonium from a solution containing plutonium Expired JPS6055800B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP55113200A JPS6055800B2 (en) 1980-08-18 1980-08-18 How to recover plutonium from a solution containing plutonium

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP55113200A JPS6055800B2 (en) 1980-08-18 1980-08-18 How to recover plutonium from a solution containing plutonium

Publications (2)

Publication Number Publication Date
JPS5737292A JPS5737292A (en) 1982-03-01
JPS6055800B2 true JPS6055800B2 (en) 1985-12-06

Family

ID=14606083

Family Applications (1)

Application Number Title Priority Date Filing Date
JP55113200A Expired JPS6055800B2 (en) 1980-08-18 1980-08-18 How to recover plutonium from a solution containing plutonium

Country Status (1)

Country Link
JP (1) JPS6055800B2 (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6282296A (en) * 1985-10-04 1987-04-15 Hitachi Ltd Pump device
JPH0359495U (en) * 1989-10-12 1991-06-12

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6282296A (en) * 1985-10-04 1987-04-15 Hitachi Ltd Pump device
JPH0359495U (en) * 1989-10-12 1991-06-12

Also Published As

Publication number Publication date
JPS5737292A (en) 1982-03-01

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