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JP4590585B2 - A method of back-extracting Am (III) and Pu (IV) in an organic solvent into a nitric acid solution with an N, N, N ', N'-tetramethyldiglycolamide (TMDGA) compound - Google Patents
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JP4590585B2 - A method of back-extracting Am (III) and Pu (IV) in an organic solvent into a nitric acid solution with an N, N, N ', N'-tetramethyldiglycolamide (TMDGA) compound - Google Patents

A method of back-extracting Am (III) and Pu (IV) in an organic solvent into a nitric acid solution with an N, N, N ', N'-tetramethyldiglycolamide (TMDGA) compound Download PDF

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JP4590585B2
JP4590585B2 JP2004172218A JP2004172218A JP4590585B2 JP 4590585 B2 JP4590585 B2 JP 4590585B2 JP 2004172218 A JP2004172218 A JP 2004172218A JP 2004172218 A JP2004172218 A JP 2004172218A JP 4590585 B2 JP4590585 B2 JP 4590585B2
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英哉 鈴木
祐二 佐々木
由美 須郷
貴海 木村
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独立行政法人 日本原子力研究開発機構
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
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    • YGENERAL 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
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    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
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原子力分野では、使用済み燃料又は高レベル放射性廃液から、3,4価のアクチノイドイオンを抽出した後に効率的に逆抽出することはプロセス開発上重要であり、本発明の方法はこれら金属を逆抽出する方法に関わる。   In the nuclear power field, it is important for process development to extract the trivalent and tetravalent actinide ions from spent fuel or high-level radioactive liquid waste, and it is important for process development. The method of the present invention back-extracts these metals. Involved in how to do.

3,4価のアクチノイドイオンを逆抽出することは、これまでには薄い硝酸溶液などを用いる方法、クエン酸、アミノポリカルボン酸などの水溶性錯形成剤を用いる方法、さらに原子価を変える方法などを用いている。   The back-extraction of trivalent and tetravalent actinide ions can be achieved by a method using a thin nitric acid solution, a method using a water-soluble complexing agent such as citric acid or aminopolycarboxylic acid, and a method of changing the valence. Etc. are used.

プロセス開発において、Np(IV),Pu(III)Pu(IV),Am(III),およびCm(m)のような3,4価のアクチノイドイオンを抽出した後に水相に逆抽出することは使用済み燃料再処理などのプロセス開発において重要な課題である。従来法の主要な課題は次のとおりである。   In process development, extracting trivalent and tetravalent actinide ions such as Np (IV), Pu (III) Pu (IV), Am (III), and Cm (m) and back-extracting them into the aqueous phase is This is an important issue in process development such as spent fuel reprocessing. The main problems of the conventional method are as follows.

(1)酸性度を薄くしすぎた場合、特にPu(IV)は水酸化物を形成し沈殿を生ずる。
(2)クエン酸、EDTA(エチレンジアミン四酢酸)のような錯形成剤では、使用で
きるpH条件が高く(pH>3)、Pu(IV)の水酸化物沈殿する可能性がある。硝酸溶液でも使用可能なシュウ酸はPu(IV)と沈殿を生成し、またDTPA(ジエチレントリアミン五酢酸)に関しては硝酸溶液への溶解度が低い(最大50mM程度)。これらの錯形成剤は下の参考文献1−3で参照できる(非特許文献1,2及び3)。
(1) When acidity is made too thin, Pu (IV) forms a hydroxide and precipitates.
(2) With complexing agents such as citric acid and EDTA (ethylenediaminetetraacetic acid), the usable pH conditions are high (pH> 3), and there is a possibility that Pu (IV) hydroxide precipitates. Oxalic acid that can also be used in a nitric acid solution forms a precipitate with Pu (IV), and DTPA (diethylenetriaminepentaacetic acid) has low solubility in nitric acid solution (up to about 50 mM). These complexing agents can be referred to in References 1-3 below (Non-Patent Documents 1, 2 and 3).

(3)原子価を変える方法をとる場合、強い還元剤を用いることになる上に溶液内反応が複雑になる。また原子価を変える方法はTODGA抽出剤のようにAn(III),(IV)ともに強く錯形成する化合物にはそのままでは使用する事ができない。
R. Malmbeck, O. Courson, G. Pagliosa, K. Romer, B. Satmark, J.P. Glatz, P. Baron: Partitioning of minor actinides from HLLW using the DIAMEX process. Part 2-"Hot" continuous counter-current experiment. Radiochim. Acta 88, 865-871(2000). Y. Zilberman, YS. Fedorov, E.N. Mishin, L.V. Sytnik, O.V. Shmidt, D.N. Kukharev, N.D. Goletsky, R.G. Glekov, Y.V. Palenik, S.Y. Sukhareva, Superpurex as a TBP-compatible process for recovery and partitioning of long-lived radionuclides from NPP spent fuel, JAERI-Conf 2002-004, P189-195. P. Baron, M. Lecomte, B. Boullis, N. Simon, D. Warin, Separation of the long lived radionuclides: Current status and future R and D program in France, Global 2003, November 11/16, New Orleans, USA (2003).
(3) When the method of changing the valence is used, a strong reducing agent is used and the reaction in the solution becomes complicated. In addition, the method of changing the valence cannot be used as it is for a compound that forms a strong complex with both An (III) and (IV), such as a TODGA extractant.
R. Malmbeck, O. Courson, G. Pagliosa, K. Romer, B. Satmark, JP Glatz, P. Baron: Partitioning of minor actinides from HLLW using the DIAMEX process. Part 2- "Hot" continuous counter-current experiment. Radiochim. Acta 88, 865-871 (2000). Y. Zilberman, YS. Fedorov, EN Mishin, LV Sytnik, OV Shmidt, DN Kukharev, ND Goletsky, RG Glekov, YV Palenik, SY Sukhareva, Superpurex as a TBP-compatible process for recovery and partitioning of long-lived radionuclides from NPP spent fuel, JAERI-Conf 2002-004, P189-195. P. Baron, M. Lecomte, B. Boullis, N. Simon, D. Warin, Separation of the long lived radionuclides: Current status and future R and D program in France, Global 2003, November 11/16, New Orleans, USA (2003).

(1)本発明の目的の錯形成剤は、0.2M硝酸濃度条件でもAn(III),(IV)の分配比を十分に下げることのできる化合物である。また、3M程度の硝酸溶液からでもPu(IV)の分配比を下げる事ができ、逆抽出の際に水酸化物形成を完全に抑制できる。(2)本発明の目的の錯形成剤は0.2M硝酸溶液に十分溶解可能であり、この時に1M TMDGAの溶液を調製する事が可能である。また濃硝酸でも十分な溶解度を示し、一方有機相には殆ど溶解しない。(3)本発明の目的の錯形成剤は2次廃棄物発生量を低減できる、炭素、水素、酸素、窒素からなる化合物である。(4)本発明の目的の錯形成剤は中性の化合物であり、錯形成時にPu(IV)と沈殿を生成しない。   (1) The complexing agent of the present invention is a compound that can sufficiently reduce the distribution ratio of An (III) and (IV) even under a 0.2M nitric acid concentration condition. Moreover, the distribution ratio of Pu (IV) can be lowered even from about 3M nitric acid solution, and hydroxide formation can be completely suppressed during back extraction. (2) The complexing agent of the present invention can be sufficiently dissolved in a 0.2 M nitric acid solution, and at this time, a 1 M TMDGA solution can be prepared. Concentrated nitric acid also shows sufficient solubility, while it hardly dissolves in the organic phase. (3) The complexing agent of the object of the present invention is a compound composed of carbon, hydrogen, oxygen, and nitrogen that can reduce the amount of secondary waste generated. (4) The complexing agent of the object of the present invention is a neutral compound, and does not produce Pu (IV) and precipitates during complex formation.

本発明においては、以上の課題を解決すべき錯形成剤を見出した。即ち、本発明は、DGA(ジグリコールアミド)化合物の一つである、TMDGA(N,N,N’,N’−テトラメチル−1,3−オキサペンタンジアミド)を開発した。即ち、本発明は、N,N,N',N'−テトラメチルジグリコールアミド(TMDGA)化合物により有機溶媒中のAm(III),Pu(IV)を硝酸溶液に逆抽出する方法である。   In the present invention, the complexing agent which should solve the above-mentioned subject was found. That is, the present invention has developed TMDGA (N, N, N ′, N′-tetramethyl-1,3-oxapentanediamide), which is one of DGA (diglycolamide) compounds. That is, the present invention is a method for back-extracting Am (III) and Pu (IV) in an organic solvent into a nitric acid solution with an N, N, N ′, N′-tetramethyldiglycolamide (TMDGA) compound.

従来の抽出剤使用に起因する欠点に対して、本発明の抽出剤の利点をまとめると、
(1)0.2M硝酸の条件でAm(III),Pu(IV)の低い分配比を
示し、3M硝酸でもPu(IV)の低い分配比を示す。
To summarize the advantages of the extractant of the present invention against the disadvantages caused by the use of conventional extractants,
(1) Low distribution ratio of Am (III) and Pu (IV) under the condition of 0.2M nitric acid, and low distribution ratio of Pu (IV) even with 3M nitric acid.

分配比とは、基本的に「有機相中の金属イオン濃度」/「水相中の金属イオン濃度」を示すが、本発明においては、有機相にある金属イオンをTMDGAによって水相に戻すことを意味するので、分配比が低い方がTMDGAの働きが強いことを示している。   The distribution ratio basically indicates “metal ion concentration in the organic phase” / “metal ion concentration in the aqueous phase”. In the present invention, the metal ions in the organic phase are returned to the aqueous phase by TMDGA. Therefore, the lower the distribution ratio, the stronger the action of TMDGA.

(2)Pu(IV)と沈殿形成しない。
(3)炭素、水素、酸素、窒素からなり構造内にリンを含まない化合物である。
(4)還元剤を加える必要がない。
(2) No precipitate formation with Pu (IV).
(3) A compound composed of carbon, hydrogen, oxygen, and nitrogen and containing no phosphorus in the structure.
(4) There is no need to add a reducing agent.

(5)水への溶解度が高く、最大1M TMDGA/3M硝酸の溶液として使用可能である。   (5) It has high solubility in water and can be used as a solution of 1M TMDGA / 3M nitric acid at maximum.

本発明においては、使用済み燃料(SF)溶解液あるいは高レベル放射性廃液(HLLW)のような硝酸水溶液から金属イオンを溶媒抽出する際に、抽出した後のAn(III),(IV)を水相に逆抽出する事ができ、プロセスに応用できる。また、高い錯形成能力を生かして、現在使用されるEDTA等に代わる放射能除染剤としても使用可能である。   In the present invention, when extracting metal ions from an aqueous nitric acid solution such as spent fuel (SF) solution or high-level radioactive waste liquid (HLLW), the extracted An (III) and (IV) are extracted from water. It can be back-extracted into phases and applied to processes. Moreover, it can be used as a radioactive decontamination agent in place of EDTA or the like currently used by making use of its high complexing ability.

又、本発明においては、SF溶解液あるいはHLLWから効率的に3,4価アクチノイドイオンを有機相より逆抽出でき、水酸化物沈殿などの問題を解決でき、円滑なプロセス運転を可能とするという本発明に特有な顕著な効果を生ずるものである。   In the present invention, the trivalent and tetravalent actinide ions can be efficiently back-extracted from the organic phase from the SF solution or HLLW, so that problems such as hydroxide precipitation can be solved, and smooth process operation is possible. The remarkable effect peculiar to this invention is produced.

実施例1
TMDGAを用いて、Pu(IV)及びAm(III)の抽出分配比を測定した。水相に各アクチノイドイオンとTMDGAを含む0.2M硝酸溶液を、有機相に0.2M TODGA/n−ドデカン溶媒を用いて、得られた分配比をTMDGA濃度に対してプロットした。その結果を図1に示す。図1に示されるように、TMDGA濃度が増加するとともにPu(IV),Am(III)分配比は減少し、TMDGA濃度0.1Mで、Pu(IV)及びAm(III)それぞれの分配比は0.01以下であった。なお、TMDGAが存在しない条件で0.2M TODGA/n−ドデカン−0.2M硝酸条件での分配比はPu(IV)が3で、Am(III)が1.46であった。したがって、TMDGAは、その濃度が低くてもPu(IV)及びAm(III)の抽出が良好に行われることを示している。
実施例2
TMDGAを用いて、Pu(IV),Am(III)の抽出分配比を測定した。水相にアクチノイドイオンと0.1M TMDGAを含む硝酸溶液、有機相に0.2M TODGA/n−ドデカン溶媒を用いて、得られた分配比を硝酸濃度に対してプロットした。その結果を図2に示す。図2に示されるように、0.1M TMDGAを含む0.64M硝酸溶液を用いて、Pu(IV),Am(III)分配比はそれぞれ0.002,0.017であり、これ以下の酸濃度条件で一括逆抽出が可能である。なお、Pu(IV)に対して、3M HNO3の条件でも分配比は0.1以下であり、この条件を用いれば、単独にPu(IV)のみを逆抽出する事が出来る。
Example 1
The extraction partition ratio of Pu (IV) and Am (III) was measured using TMDGA. Using 0.2M nitric acid solution containing each actinide ion and TMDGA in the aqueous phase and 0.2M TODGA / n-dodecane solvent in the organic phase, the obtained distribution ratio was plotted against the TMDGA concentration. The result is shown in FIG. As shown in FIG. 1, as the TMDGA concentration increases, the Pu (IV), Am (III) distribution ratio decreases, and at the TMDGA concentration of 0.1 M, the distribution ratios of Pu (IV) and Am (III) are as follows. It was 0.01 or less. In the absence of TMDGA, the distribution ratio under the conditions of 0.2M TODGA / n-dodecane-0.2M nitric acid was 3 for Pu (IV) and 1.46 for Am (III). Therefore, TMDGA shows that Pu (IV) and Am (III) are well extracted even at low concentrations.
Example 2
The extraction partition ratio of Pu (IV) and Am (III) was measured using TMDGA. Using a nitric acid solution containing actinide ions and 0.1M TMDGA in the aqueous phase and a 0.2M TODGA / n-dodecane solvent in the organic phase, the obtained distribution ratio was plotted against the nitric acid concentration. The result is shown in FIG. As shown in FIG. 2, using a 0.64M nitric acid solution containing 0.1M TMDGA, Pu (IV) and Am (III) distribution ratios are 0.002 and 0.017, respectively. Batch back extraction is possible under concentration conditions. Note that the distribution ratio is 0.1 or less with respect to Pu (IV) even under the condition of 3M HNO 3 , and using this condition, only Pu (IV) can be back-extracted alone.

即ち、3価のアクチノイドイオン(Am(III))と4価のアクチノイドイオン(Pu(IV))とが共存する系においては、図2中のプロットでPuの分配比が低く、Amの分配比が高い条件下においては、選択的にPuのみ水相に分離回収することができることを意味している。   That is, in a system in which a trivalent actinoid ion (Am (III)) and a tetravalent actinoid ion (Pu (IV)) coexist, the distribution ratio of Pu is low in the plot in FIG. This means that under high conditions, only Pu can be separated and recovered in the aqueous phase.

Pu(IV),及びAm(III)分配比のTMDGA濃度依存性(有機相;0.2M TODGA/n−ドデカン、水相;TMDGA/0.2M硝酸)を示す図である。It is a figure which shows TMDGA density | concentration dependence (Organic phase; 0.2M TODGA / n-dodecane, aqueous phase; TMDGA / 0.2M nitric acid) of Pu (IV) and Am (III) distribution ratio. Pu(IV),及びAm(III)分配比の硝酸濃度依存性(有機相;0.2M TODGA/n−ドデカン、水相;0.1M TMDGA/硝酸)を示す図である。It is a figure which shows the nitric acid concentration dependence of the Pu (IV) and Am (III) distribution ratio (organic phase; 0.2M TODGA / n-dodecane, aqueous phase; 0.1M TMDGA / nitric acid).

Claims (1)

TODGA(N,N,N',N'−テトラオクチル−1,3−オキサペンタンジアミド)を抽出剤として用いてn−ドデカン溶媒に抽出した後のAm(III),Pu(IV)の3,4価のアクチノイドイオンをTMDGA(N,N,N’,N’−テトラメチル−ジグリコールアミド)により、硝酸溶液中に逆抽出する方法。 After extraction with TODGA (N, N, N ′, N′-tetraoctyl-1,3-oxapentanediamide) as an extractant into n-dodecane solvent, Am (III), Pu (IV) 3, a tetravalent actinide ions, TMDGA (N, N, N ', N'- tetramethyl - diglycol amides) by a method of stripping the nitric acid solution.
JP2004172218A 2004-06-10 2004-06-10 A method of back-extracting Am (III) and Pu (IV) in an organic solvent into a nitric acid solution with an N, N, N ', N'-tetramethyldiglycolamide (TMDGA) compound Expired - Fee Related JP4590585B2 (en)

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JP4534000B2 (en) * 2004-09-02 2010-09-01 独立行政法人 日本原子力研究開発機構 A method of back-extracting Am (III) and Pu (IV) in an organic solvent using a nitric acid solution having a concentration of 0.1 M or more in which an N, N-dipropyldiglycolamidic acid (PDGAA) compound is dissolved.
JP4604226B2 (en) * 2005-11-16 2011-01-05 独立行政法人 日本原子力研究開発機構 Method for quantitative extraction and back extraction of neptunium in nitric acid solution with DGA (diglycolamide) compound
FR2948384B1 (en) * 2009-07-27 2011-09-23 Commissariat Energie Atomique INCREASING THE SEPARATION FACTOR BETWEEN AMERICIUM AND CURIUM AND / OR BETWEEN LANTHANIDES IN A LIQUID-LIQUID EXTRACTION OPERATION
JP5526434B2 (en) * 2010-01-20 2014-06-18 独立行政法人日本原子力研究開発機構 N, N, N ′, N′-tetraalkyl-3,6-dioxaoctane-1,8-diamide (DOODA) and TADGA (N, N, N ′, N′-tetraalkyl-diglycolamide) Mutual separation of Am, Cm and Sm, Eu, Gd used together
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