JPH09243796A - Method for processing reactor fuel reprocessed waste liquid - Google Patents
Method for processing reactor fuel reprocessed waste liquidInfo
- Publication number
- JPH09243796A JPH09243796A JP5590696A JP5590696A JPH09243796A JP H09243796 A JPH09243796 A JP H09243796A JP 5590696 A JP5590696 A JP 5590696A JP 5590696 A JP5590696 A JP 5590696A JP H09243796 A JPH09243796 A JP H09243796A
- Authority
- JP
- Japan
- Prior art keywords
- americium
- extractant
- waste liquid
- solution
- curium
- 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- Withdrawn
Links
- 239000007788 liquid Substances 0.000 title claims abstract description 18
- 238000000034 method Methods 0.000 title claims abstract description 16
- 239000002699 waste material Substances 0.000 title claims abstract description 15
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 11
- 238000012545 processing Methods 0.000 title description 2
- 229910052695 Americium Inorganic materials 0.000 claims abstract description 29
- LXQXZNRPTYVCNG-UHFFFAOYSA-N americium atom Chemical compound [Am] LXQXZNRPTYVCNG-UHFFFAOYSA-N 0.000 claims abstract description 29
- 229910052747 lanthanoid Inorganic materials 0.000 claims abstract description 21
- 150000002602 lanthanoids Chemical class 0.000 claims abstract description 21
- 229910052685 Curium Inorganic materials 0.000 claims abstract description 17
- AEMRFAOFKBGASW-UHFFFAOYSA-N Glycolic acid Chemical compound OCC(O)=O AEMRFAOFKBGASW-UHFFFAOYSA-N 0.000 claims abstract description 10
- STCOOQWBFONSKY-UHFFFAOYSA-N tributyl phosphate Chemical compound CCCCOP(=O)(OCCCC)OCCCC STCOOQWBFONSKY-UHFFFAOYSA-N 0.000 claims abstract description 6
- 239000003085 diluting agent Substances 0.000 claims abstract description 5
- SNRUBQQJIBEYMU-UHFFFAOYSA-N dodecane Chemical compound CCCCCCCCCCCC SNRUBQQJIBEYMU-UHFFFAOYSA-N 0.000 claims abstract description 4
- 239000012046 mixed solvent Substances 0.000 claims abstract description 4
- 229940094933 n-dodecane Drugs 0.000 claims abstract description 4
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 claims description 18
- 238000012958 reprocessing Methods 0.000 claims description 9
- 235000011121 sodium hydroxide Nutrition 0.000 claims description 6
- QPCDCPDFJACHGM-UHFFFAOYSA-N N,N-bis{2-[bis(carboxymethyl)amino]ethyl}glycine Chemical compound OC(=O)CN(CC(O)=O)CCN(CC(=O)O)CCN(CC(O)=O)CC(O)=O QPCDCPDFJACHGM-UHFFFAOYSA-N 0.000 claims description 4
- 229960003330 pentetic acid Drugs 0.000 claims description 4
- 239000003795 chemical substances by application Substances 0.000 abstract description 7
- 238000000926 separation method Methods 0.000 abstract description 4
- 230000001105 regulatory effect Effects 0.000 abstract 3
- 239000003518 caustics Substances 0.000 abstract 1
- 238000010129 solution processing Methods 0.000 abstract 1
- 238000000605 extraction Methods 0.000 description 10
- 229910052770 Uranium Inorganic materials 0.000 description 4
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 4
- 229910052684 Cerium Inorganic materials 0.000 description 3
- 229910052693 Europium Inorganic materials 0.000 description 3
- 229910052688 Gadolinium Inorganic materials 0.000 description 3
- 229910052779 Neodymium Inorganic materials 0.000 description 3
- 229910052778 Plutonium Inorganic materials 0.000 description 3
- 229910052772 Samarium Inorganic materials 0.000 description 3
- GWXLDORMOJMVQZ-UHFFFAOYSA-N cerium Chemical compound [Ce] GWXLDORMOJMVQZ-UHFFFAOYSA-N 0.000 description 3
- OGPBJKLSAFTDLK-UHFFFAOYSA-N europium atom Chemical compound [Eu] OGPBJKLSAFTDLK-UHFFFAOYSA-N 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 description 3
- 229960004275 glycolic acid Drugs 0.000 description 3
- 239000002927 high level radioactive waste Substances 0.000 description 3
- QEFYFXOXNSNQGX-UHFFFAOYSA-N neodymium atom Chemical compound [Nd] QEFYFXOXNSNQGX-UHFFFAOYSA-N 0.000 description 3
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 3
- KZUNJOHGWZRPMI-UHFFFAOYSA-N samarium atom Chemical compound [Sm] KZUNJOHGWZRPMI-UHFFFAOYSA-N 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- NBIIXXVUZAFLBC-UHFFFAOYSA-N Phosphoric acid Chemical compound OP(O)(O)=O NBIIXXVUZAFLBC-UHFFFAOYSA-N 0.000 description 2
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 2
- 239000008346 aqueous phase Substances 0.000 description 2
- 239000003153 chemical reaction reagent Substances 0.000 description 2
- 239000012074 organic phase Substances 0.000 description 2
- 238000005192 partition Methods 0.000 description 2
- 239000012071 phase Substances 0.000 description 2
- 239000004215 Carbon black (E152) Substances 0.000 description 1
- RPNUMPOLZDHAAY-UHFFFAOYSA-N Diethylenetriamine Chemical compound NCCNCCN RPNUMPOLZDHAAY-UHFFFAOYSA-N 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 229910000147 aluminium phosphate Inorganic materials 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 229910052732 germanium Inorganic materials 0.000 description 1
- GNPVGFCGXDBREM-UHFFFAOYSA-N germanium atom Chemical compound [Ge] GNPVGFCGXDBREM-UHFFFAOYSA-N 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 150000002823 nitrates Chemical class 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 239000010815 organic waste Substances 0.000 description 1
- LQPLDXQVILYOOL-UHFFFAOYSA-I pentasodium;2-[bis[2-[bis(carboxylatomethyl)amino]ethyl]amino]acetate Chemical compound [Na+].[Na+].[Na+].[Na+].[Na+].[O-]C(=O)CN(CC([O-])=O)CCN(CC(=O)[O-])CCN(CC([O-])=O)CC([O-])=O LQPLDXQVILYOOL-UHFFFAOYSA-I 0.000 description 1
- 239000000700 radioactive tracer Substances 0.000 description 1
- 239000004065 semiconductor Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Landscapes
- Extraction Or Liquid Replacement (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、原子炉燃料の再処
理によって生ずる廃液の処理方法に関し、特にランタニ
ド及び超ウラン元素を含む高レベル放射性廃液からアメ
リシウム及びキュリウムを分離する方法に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating waste liquid generated by reprocessing of nuclear fuel, and more particularly to a method for separating americium and curium from a high level radioactive waste liquid containing lanthanides and transuranium elements.
【０００２】[0002]
【従来の技術】原子炉燃料として広く使用されているウ
ラン燃料は、核反応により核分裂性物質であるプルトニ
ウムを生じ、その再処理によりプルトニウム及びウラン
が回収されている。しかしながら前述の核反応によりア
メリシウムやキュリウム等も生じており、これらは前記
再処理に際しランタニドと一緒に高レベル放射性廃棄物
となっている。この高レベル放射性廃棄物はかなりの長
期間厳重に保管しなければならないため、できるだけ容
量が少ない方がよい。又アメリシウムやキュリウムは高
速増殖炉で燃焼可能な有用物質であるので、その分離が
推奨されている。2. Description of the Related Art Uranium fuel, which is widely used as a nuclear reactor fuel, produces plutonium which is a fissile material by a nuclear reaction, and plutonium and uranium are recovered by reprocessing the same. However, the above-mentioned nuclear reaction also produces americium, curium, and the like, which are high-level radioactive wastes together with lanthanides during the reprocessing. This high-level radioactive waste must be stored strictly for a long period of time, so it is better to have the smallest possible volume. Further, since americium and curium are useful substances that can be burned in a fast breeder reactor, their separation is recommended.
【０００３】このようなアメリシウムとキュリウムの分
離方法としては、次のようなプロセスが知られている。
即ち燃料再処理廃液のｐＨを苛性ソウダ（ＮａＯＨ）で
１．５に調整し、これを０．４Ｍのジ−２−エチルヘキ
シル リン酸（Ｄ２ＥＨＰＡ）と０．４Ｍのリン酸トリ
ブチル及び希釈剤としてのｎ−炭化水素からなる抽出剤
に２５℃で１０分間接触させ、アメリシウム及びキュリ
ウムを抽出する。しかる後、逆抽出剤として苛性ソウダ
でｐＨを３．３に調整した０．５Ｍのヒドロキシ酢酸と
０．０８９Ｍのジエチレントリアミン五酢酸との混合溶
媒を用いてこのアメリシウム及びキュリウムを逆抽出す
る。逆抽出条件は、有機相である抽出剤と水相である逆
抽出剤との比を４、温度を２５℃、接触時間は１０分で
ある。なお、同様な分離方法が米国特許第３４６３６１
９号明細書に記載されている。The following process is known as a method for separating such americium and curium.
That is, the pH of the fuel reprocessing waste liquid was adjusted to 1.5 with caustic soda (NaOH), and this was adjusted to 0.4M di-2-ethylhexylphosphoric acid (D2EHPA) and 0.4M tributyl phosphate and as a diluent. Americium and curium are extracted by contacting with an extractant composed of n-hydrocarbon at 25 ° C. for 10 minutes. Then, the americium and curium are back-extracted using a mixed solvent of 0.5M hydroxyacetic acid whose pH is adjusted to 3.3 with caustic soda and 0.089M diethylenetriaminepentaacetic acid as a back extractor. The back extraction conditions are as follows: the ratio of the organic phase extractant to the aqueous phase back extractant is 4, the temperature is 25 ° C., and the contact time is 10 minutes. A similar separation method is disclosed in US Pat. No. 346361.
No. 9 is described.
【０００４】[0004]
【発明が解決しようとする課題】しかるに、前述したア
メリシウム及びキュリウムの分離方法では、抽出操作及
び逆抽出操作の接触時間が１０分と長く、又ジ−２−エ
チルヘキシル リン酸、リン酸トリブチル及びジエチレ
ントリアミン五酢酸の濃度が高く、廃液量が多くなると
いう問題がある。従って、本発明は接触時間等の処理時
間が短く、且つ有機廃棄物の発生量の少ない原子炉燃料
再処理廃液からのアメリシウム及びキュリウムの分離方
法を提供することを課題とするものである。However, in the above-described method for separating americium and curium, the contact time for the extraction operation and the back extraction operation is as long as 10 minutes, and di-2-ethylhexylphosphoric acid, tributyl phosphate and diethylenetriamine are used. There is a problem that the concentration of pentaacetic acid is high and the amount of waste liquid increases. Therefore, it is an object of the present invention to provide a method for separating americium and curium from a nuclear reactor fuel reprocessing waste liquid which has a short treatment time such as contact time and produces a small amount of organic waste.
【０００５】[0005]
【課題を解決するための手段】如上の課題を解決するた
め、本発明によれば、ランタニド、アメリシウム及びキ
ュリウムを含む原子炉燃料再処理廃液のｐＨを先ず２〜
３に調整し、次に０．３Ｍのジ−２−エチルヘキシル
リン酸（Di-2-ethylhexyl phosphoric acid，Ｄ２ＥＨ
ＰＡ）及び０．２Ｍのリン酸トリブチル（tributhyl ph
oshate）並びに希釈剤としてのｎ−ドデカンからなる混
合溶媒を抽出剤としてこれに前述の調整済み廃液を室温
条件下で５分間接触させ、ランタニド、アメリシウム及
びキュリウムを抽出剤に抽出する。しかる後、１Ｍのグ
リコール酸と苛性ソウダでｐＨを〜３に調整した０．０
１Ｍのジエチレントリアミン五酢酸五ナトリウム（pent
asodium diethylenetriaminepentaacetate，Ｎａ５ＤＴ
ＰＡ）の溶液を逆抽出剤としてこれと前述の抽出剤（ア
メリシウム等を含む）とを液温４０〜６０℃で１分間接
触させ、アメリシウムとキュリウムとを逆抽出し、ラン
タニドから分離する。In order to solve the above-mentioned problems, according to the present invention, the pH of the nuclear fuel reprocessing waste liquid containing lanthanide, americium and curium is first adjusted to 2 to 2.
Adjusted to 3, then 0.3M di-2-ethylhexyl
Phosphoric acid (Di-2-ethylhexyl phosphoric acid, D2EH
PA) and 0.2M tributyl phosphate (tributhyl ph)
ashate) and n-dodecane as a diluent are used as an extractant, and the prepared waste liquid is brought into contact with the extractant for 5 minutes at room temperature to extract lanthanide, americium and curium into the extractant. Thereafter, the pH was adjusted to ˜3 with 1 M glycolic acid and caustic soda, and then adjusted to 0.0.
1M diethylenetriaminepentaacetic acid pentasodium (pent
asodium diethylenetriaminepentaacetate, Na5DT
The solution of PA) is used as a back extractant and this extractant (including americium, etc.) is brought into contact with the solution at a liquid temperature of 40 to 60 ° C. for 1 minute to back extract americium and curium and separate them from the lanthanide.
【０００６】[0006]
【発明の実施の形態】以下本発明の実施形態を説明す
る。原子炉燃料の再処理方法としては、比較的広く採用
されているピューレックス法を想定し、軽水炉燃料のウ
ラン燃料をピューレックス法により処理してウラン、プ
ルトニュウム及びランタニドを除く核分裂生成物を抽出
した後の水相であるラフィネート（抽出残液）を本発明
方法により処理してアメリシウム及びキュリウムを分離
する場合を説明する。先ず前述のラフィネートを模擬し
た模擬ラフィネートを、ランタニドとしてのセリウム
（Ｃｅ），ネオジム（Ｎｄ），サマリウム（Ｓｍ）、ユ
ーロピウム（Ｅｕ），ガドリニウム（Ｇｄ）の硝酸塩と
トレーサとして添加されたアメリシウム（Ａｍ）の水溶
液を硝酸を用いてｐＨ1.3〜3.0に調整して作成した。ラ
ンタニド濃度は次のとおりである。 セリウム ９７５ppm ネオジム １５７０ppm サマリウム ４５７ppm ユーロピウム ５６ppm ガドリニウム ４５ppmEmbodiments of the present invention will be described below. As a method for reprocessing nuclear fuel, the Purex method, which is relatively widely adopted, is assumed, and fission products other than uranium, plutonium and lanthanide are extracted by processing the uranium fuel of the light water reactor fuel by the Purex method. The case where the raffinate (extraction residual liquid) which is the subsequent aqueous phase is treated by the method of the present invention to separate americium and curium will be described. First, a simulated raffinate simulating the above-described raffinate was prepared by adding nitrates of cerium (Ce), neodymium (Nd), samarium (Sm), europium (Eu), and gadolinium (Gd) as lanthanides and americium (Am) added as a tracer. Was prepared by adjusting the pH to 1.3 to 3.0 using nitric acid. The lanthanide concentrations are as follows. Cerium 975ppm Neodymium 1570ppm Samarium 457ppm Europium 56ppm Gadolinium 45ppm
【０００７】抽出剤として、ｎ−ドデカンを希釈剤とし
た０．３Ｍのジ−２−エチルヘキシル リン酸と０．２
Ｍのリン酸トリブチルの混合溶媒を用いる。逆抽出剤と
しては、１Ｍのグリコール酸と苛性ソウダでｐＨを〜３
に調整した０．０１Ｍのジエチレントリアミン五酢酸五
ナトリウムの溶液を用い、前述の模擬ラフィネートを図
１に示すフローチャートに従って処理した。即ち、模擬
ラフィネートと抽出剤とを混合し、液温２０℃で５分間
接触させて抽出操作を行った。そして、水相のランタニ
ドは発行分光分析計で定量し、水相、有機相のアメリシ
ウムはゲルマニウム半導体検出器で定量する。ところで
以上のランタニドとアメリシウムの分配係数と分配平衡
時のｐＨとの関係は図２のように示される。ｐＨが１．
１付近の２点は、初期ｐＨが１．３〜１．５に調整され
た系であり、残りの４点は初期ｐＨが２．４〜３．０に
調整されたものである。初期ｐＨを２．０以上に調整す
ると、ランタニドの分配係数が１０以上になる。即ち、
以上のランタニドとアメリシウムは、十分に抽出剤に抽
出される。As an extractant, 0.3 M di-2-ethylhexyl phosphoric acid with n-dodecane as a diluent and 0.2
A mixed solvent of M tributyl phosphate is used. As a back extractor, the pH is adjusted to ~ 3 with 1 M glycolic acid and caustic soda.
The above simulated raffinate was treated according to the flow chart shown in FIG. 1 using a solution of 0.01 M diethylenetriaminepentaacetic acid pentasodium adjusted to 1. That is, the simulated raffinate and the extractant were mixed and brought into contact with each other at a liquid temperature of 20 ° C. for 5 minutes to carry out an extraction operation. Then, the lanthanide in the water phase is quantified by an emission spectrophotometer, and the americium in the water phase and the organic phase is quantified by a germanium semiconductor detector. By the way, the relationship between the distribution coefficient of lanthanide and americium and the pH at the distribution equilibrium is shown in FIG. pH is 1.
Two points near 1 are the systems whose initial pH was adjusted to 1.3 to 1.5, and the remaining four points were those whose initial pH was adjusted to 2.4 to 3.0. When the initial pH is adjusted to 2.0 or higher, the distribution coefficient of lanthanide becomes 10 or higher. That is,
The above lanthanides and americium are sufficiently extracted by the extractant.
【０００８】次にランタニドとアメリシウムを抽出した
抽出剤と前述の逆抽出剤とを４０〜６０℃に加温し、混
合後、所定の接触時間で逆抽出操作を実施した。ここで
抽出剤と逆抽出剤との間のランタニドの分配係数と接触
時間は図３に示されている。図においで白抜きの記号
は、室温での接触時間を示し、塗りつぶしの記号は、５
５℃に加温した状態での接触時間を示している。本発明
では、逆抽出操作において４０〜６０℃に加熱されてい
るので、従来の同様の分配係数は１分程度の接触時間で
得られる。なお、このときのランタニドとアメリシウム
の分離係数は次のとおりとなる。 セリウム ９１ ネオジム １９ サマリウム ２３ ユーロピウム ３３ ガドリニウム ２３Next, the extractant from which lanthanide and americium were extracted and the above-mentioned back extractor were heated to 40 to 60 ° C., and after mixing, a back extraction operation was carried out at a predetermined contact time. Here, the partition coefficient and contact time of the lanthanide between the extractant and the back extractant are shown in FIG. In the figure, the open symbols indicate the contact time at room temperature, and the filled symbols indicate 5
The contact time in the state heated at 5 ° C is shown. In the present invention, since it is heated to 40 to 60 ° C. in the back-extraction operation, a conventional similar distribution coefficient can be obtained in a contact time of about 1 minute. The separation factors of lanthanide and americium at this time are as follows. Cerium 91 Neodymium 19 Samarium 23 Europium 33 Gadolinium 23
【０００９】[0009]
【発明の効果】以上説明したように、本発明によれば、
以上のように特別の組成の抽出剤及び逆抽出剤を使用
し、逆抽出操作において加温するので接触時間が短くて
すみ、アメリシウム及びキュリウムの分離を短時間で行
うことができる。又、抽出剤のリン酸系試薬及び逆抽出
剤の試薬の濃度が小さくてすむので、抽出剤の廃液量を
減量することができる。As described above, according to the present invention,
As described above, the extractant and the back extractant having the special composition are used, and the heating is performed in the back extraction operation, so that the contact time is short, and the americium and the curium can be separated in a short time. Further, since the concentrations of the phosphoric acid type reagent of the extracting agent and the reagent of the back extracting agent can be small, the amount of the extracting agent waste liquid can be reduced.
【図１】本発明方法の１実施形態のフローチャートであ
る。1 is a flow chart of one embodiment of the method of the present invention.
【図２】本発明方法の抽出操作における分配係数とｐＨ
の関係を示すグラフである。FIG. 2 Partition coefficient and pH in the extraction operation of the method of the present invention
6 is a graph showing the relationship of.
【図３】本発明方法の逆抽出操作における分配係数と接
触時間の関係を示すグラフである。FIG. 3 is a graph showing the relationship between the distribution coefficient and the contact time in the back extraction operation of the method of the present invention.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 藤岡 綱昭 東京都千代田区丸の内二丁目５番１号 三 菱重工業株式会社内 (72)発明者 波多野 守 東京都千代田区丸の内二丁目５番１号 三 菱重工業株式会社内 ─────────────────────────────────────────────────── ─── Continuation of front page (72) Inventor Tsunaaki Fujioka 2-5-1, Marunouchi, Chiyoda-ku, Tokyo Sanryo Heavy Industries Co., Ltd. (72) Mamoru Hatano 2-5-1, Marunouchi, Chiyoda-ku, Tokyo Sanryo Heavy Industries Co., Ltd.
Claims (1)
ムを含む原子炉燃料再処理廃液のｐＨを先ず２〜３に調
整し、次に０．３Ｍのジ−２−エチルヘキシル リン酸
及び０．２Ｍのリン酸トリブチル並びに希釈剤としての
ｎ−ドデカンからなる混合溶媒を抽出剤としてこれに前
述の調整済み廃液を室温条件下で、５分間接触させ、ラ
ンタニド、アメリシウム及びキュリウムを抽出剤に抽出
し、しかる後、１Ｍのグリコール酸と苛性ソウダでｐＨ
を〜３に調整した０．０１Ｍのジエチレントリアミン五
酢酸五ナトリウムとの溶液を逆抽出剤としてこれとアメ
リシウム等を含む前記抽出剤とを液温４０〜６０℃で１
分間接触させ、アメリシウムとキュリウムとを逆抽出
し、ランタニドから分離することを特徴とする原子炉燃
料再処理廃液の処理方法。1. The pH of a reactor fuel reprocessing waste liquid containing lanthanide, americium, and curium is first adjusted to 2-3, and then 0.3M di-2-ethylhexylphosphoric acid and 0.2M tributyl phosphate. Also, a mixed solvent consisting of n-dodecane as a diluent is used as an extractant, and the adjusted waste liquid is brought into contact with this for 5 minutes under room temperature conditions to extract lanthanide, americium and curium into the extractant, and then 1M. PH with glycolic acid and caustic soda
As a back extractant with a solution of 0.01 M diethylenetriaminepentaacetic acid pentasodium adjusted to 3 to 3 and the extractant containing americium and the like at a liquid temperature of 40 to 60 ° C.
A method for treating waste liquid for reprocessing of nuclear reactor fuel, which comprises contacting for a minute, back-extracting americium and curium, and separating from lanthanide.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5590696A JPH09243796A (en) | 1996-03-13 | 1996-03-13 | Method for processing reactor fuel reprocessed waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5590696A JPH09243796A (en) | 1996-03-13 | 1996-03-13 | Method for processing reactor fuel reprocessed waste liquid |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH09243796A true JPH09243796A (en) | 1997-09-19 |
Family
ID=13012167
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5590696A Withdrawn JPH09243796A (en) | 1996-03-13 | 1996-03-13 | Method for processing reactor fuel reprocessed waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH09243796A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114113284A (en) * | 2021-11-26 | 2022-03-01 | 中国辐射防护研究院 | Analysis method of yttrium-90 as americium and curium chemical separation tracer |
-
1996
- 1996-03-13 JP JP5590696A patent/JPH09243796A/en not_active Withdrawn
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114113284A (en) * | 2021-11-26 | 2022-03-01 | 中国辐射防护研究院 | Analysis method of yttrium-90 as americium and curium chemical separation tracer |
| CN114113284B (en) * | 2021-11-26 | 2023-10-20 | 中国辐射防护研究院 | Analysis method of yttrium-90 as americium and curium chemical separation tracer |
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| A300 | Withdrawal of application because of no request for examination |
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