JPH0254732A - Method for eluting technetium from activated carbon - Google Patents
Method for eluting technetium from activated carbonInfo
- Publication number
- JPH0254732A JPH0254732A JP63203765A JP20376588A JPH0254732A JP H0254732 A JPH0254732 A JP H0254732A JP 63203765 A JP63203765 A JP 63203765A JP 20376588 A JP20376588 A JP 20376588A JP H0254732 A JPH0254732 A JP H0254732A
- Authority
- JP
- Japan
- Prior art keywords
- activated carbon
- technetium
- soln
- nuclear fuel
- spent nuclear
- 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.)
- Pending
Links
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 title claims abstract description 64
- 229910052713 technetium Inorganic materials 0.000 title claims description 34
- GKLVYJBZJHMRIY-UHFFFAOYSA-N technetium atom Chemical compound [Tc] GKLVYJBZJHMRIY-UHFFFAOYSA-N 0.000 title claims description 33
- 238000000034 method Methods 0.000 title claims description 11
- -1 thiocyanate ions Chemical class 0.000 claims description 10
- ZMZDMBWJUHKJPS-UHFFFAOYSA-N hydrogen thiocyanate Natural products SC#N ZMZDMBWJUHKJPS-UHFFFAOYSA-N 0.000 claims description 5
- 229910052740 iodine Inorganic materials 0.000 claims description 5
- 239000011630 iodine Substances 0.000 claims description 5
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract description 11
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract description 8
- 229910017604 nitric acid Inorganic materials 0.000 abstract description 8
- 238000001179 sorption measurement Methods 0.000 abstract description 7
- 239000003480 eluent Substances 0.000 abstract description 5
- 238000006396 nitration reaction Methods 0.000 abstract description 4
- 238000012958 reprocessing Methods 0.000 abstract description 4
- ZMZDMBWJUHKJPS-UHFFFAOYSA-M Thiocyanate anion Chemical compound [S-]C#N ZMZDMBWJUHKJPS-UHFFFAOYSA-M 0.000 abstract description 3
- XMBWDFGMSWQBCA-UHFFFAOYSA-M iodide Chemical compound [I-] XMBWDFGMSWQBCA-UHFFFAOYSA-M 0.000 abstract description 3
- 238000007796 conventional method Methods 0.000 abstract description 2
- 238000004880 explosion Methods 0.000 abstract description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 2
- 230000003247 decreasing effect Effects 0.000 abstract 1
- 239000002699 waste material Substances 0.000 abstract 1
- 238000010828 elution Methods 0.000 description 11
- 239000002927 high level radioactive waste Substances 0.000 description 6
- 239000007788 liquid Substances 0.000 description 6
- 238000000926 separation method Methods 0.000 description 3
- 230000015572 biosynthetic process Effects 0.000 description 2
- 239000003153 chemical reaction reagent Substances 0.000 description 2
- 230000007613 environmental effect Effects 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 238000011084 recovery Methods 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 239000003054 catalyst Substances 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000005755 formation reaction Methods 0.000 description 1
- 230000002401 inhibitory effect Effects 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 150000002894 organic compounds Chemical class 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- BASFCYQUMIYNBI-UHFFFAOYSA-N platinum Chemical group [Pt] BASFCYQUMIYNBI-UHFFFAOYSA-N 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000006228 supernatant Substances 0.000 description 1
- 238000003786 synthesis reaction Methods 0.000 description 1
- 150000003495 technetium Chemical class 0.000 description 1
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
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
Landscapes
- Manufacture And Refinement Of Metals (AREA)
Abstract
Description
【発明の詳細な説明】 （産業上の利用分野） 本発明は活性炭からテクネチウムの溶出方法に関する。[Detailed description of the invention] (Industrial application field) The present invention relates to a method for eluting technetium from activated carbon.
より詳しくは、本発明は、使用済核燃料の再処理によっ
て発生する高レベル放射性廃液、使用済核燃料溶解液等
のテクネチウムを含む溶液からテクネチウムを吸着分離
した活性炭からテクネチウムを溶出する方法に関する。More specifically, the present invention relates to a method for eluting technetium from activated carbon that adsorbs and separates technetium from a solution containing technetium, such as a high-level radioactive waste liquid generated by reprocessing spent nuclear fuel or a spent nuclear fuel solution.
（従来の技術）
テクネチウムは、天然には全く存在しない元素で、原子
炉や加速装置によって人工的に得られる元素であるが、
使用済核燃料の再処理に伴って発生する高レベル放射性
廃液中又は使用済核燃料溶解液中には、使用済核燃料１
トン当り約８００ｇが含まれている。高レベル放射性廃
液又は使用済核燃料溶解液からのテクネチウムの分離回
収は、高レベル放射性廃液をガラス固化体として地層処
分する場合の長期にわたる環境影響を出来るだけ少なく
するという観点から、また、回収したテクネチウムを鋼
材の腐食防止、或いは白金族元素と同様に有機化合物の
合成分野での触媒として有効に利用出来るという観点か
ら、最近特に注目されている。このため、高レベル放射
性廃液又は使用済核燃料溶解液からのテクネチウムの分
離回収は特に有効である。(Prior technology) Technetium is an element that does not exist in nature at all, and is obtained artificially through nuclear reactors and accelerators.
Spent nuclear fuel 1 is contained in the high-level radioactive waste liquid or spent nuclear fuel solution generated during the reprocessing of spent nuclear fuel.
Contains about 800g per ton. Separation and recovery of technetium from high-level radioactive waste liquid or spent nuclear fuel solution is carried out from the viewpoint of minimizing the long-term environmental impact when high-level radioactive waste liquid is disposed of as a vitrified substance in geological formations, and also from the viewpoint of minimizing the long-term environmental impact of the collected technetium. Recently, it has been attracting particular attention from the viewpoint that it can be effectively used for preventing corrosion of steel materials or as a catalyst in the synthesis of organic compounds like platinum group elements. For this reason, separation and recovery of technetium from high-level radioactive waste liquid or spent nuclear fuel solution is particularly effective.
テクネチウムの分離回収法としては、従来法よりもすぐ
れた方法として、活性炭による吸着分離法が発明されて
いるが（特願昭６３−３７６２５） 、この方法におけ
る活性炭からのテクネチウムの溶出には４Ｍ以上の硝酸
の使用が検討されてきた。As a method for separating and recovering technetium, an adsorption separation method using activated carbon has been invented as a method superior to conventional methods (Japanese Patent Application No. 63-37625). The use of nitric acid has been considered.
このテクネチウム溶出法の欠点は、テクネチウムの溶出
効率が比較的低いこと、濃い濃度の硝酸溶液の使用によ
って活性炭の吸着性能が低下し、活性炭の再利用が阻害
されること、及び活性炭のニトロ化が多少なりとも進行
し、爆発などの危険性が高まることである。The disadvantages of this technetium elution method are that the elution efficiency of technetium is relatively low, the use of a concentrated nitric acid solution reduces the adsorption performance of activated carbon, inhibiting the reuse of activated carbon, and the nitration of activated carbon is As the situation progresses, the risk of explosion, etc. increases.
（発明が解決しようとする課題）
本発明の目的は、このような欠点のない活性炭からのテ
クネチウムの溶出方法を提供することである。(Problems to be Solved by the Invention) An object of the present invention is to provide a method for eluting technetium from activated carbon without such drawbacks.
（課題を解決するための手段）
本願発明者は、鋭意研究の結果、テクネチウムを吸着さ
せた活性炭にチオシアン酸イオン又はヨウ素イオンを含
む溶液を接触させることによってテクネチウムを活性炭
から溶出できることを発見し、この方法において、テク
ネチウムの溶出効率が高く、硝酸を使用する必要がない
ことから、活性炭の吸着性能の低下やニトロ化の恐れも
なく、テクネチウムを活性炭から溶出できることを発見
し、本発明の目的を達成した。(Means for Solving the Problems) As a result of intensive research, the inventor of the present application discovered that technetium can be eluted from activated carbon by contacting activated carbon adsorbed with technetium with a solution containing thiocyanate ions or iodine ions, In this method, the elution efficiency of technetium is high and there is no need to use nitric acid, so it was discovered that technetium can be eluted from activated carbon without the risk of deterioration of the adsorption performance of activated carbon or nitration. Achieved.
すなわち、本願発明のテクネチウムの溶出方法は、使用
済核燃料の再処理によって発生する高レベル放射性廃液
、使用済核燃料溶解液等のテクネチウムを含む溶液から
、活性炭によりテクネチウムを吸着分離した後、この活
性炭からテクネチウムを溶出するため、溶出剤としてチ
オシアン酸イオン又はヨウ素イオンを含む溶液を使用す
ることを特徴とする。That is, the technetium elution method of the present invention involves adsorbing and separating technetium from a solution containing technetium, such as a high-level radioactive waste liquid generated by reprocessing spent nuclear fuel or a spent nuclear fuel solution, using activated carbon. In order to elute technetium, a solution containing thiocyanate ions or iodine ions is used as an eluent.
従って、本発明は、テクネチウムを吸着させた活性炭に
チオシアン酸イオン又はヨウ素イオンを含む溶液を接触
させることによって、テクネチウムを活性炭から溶出す
る方法から成る。Therefore, the present invention comprises a method of eluting technetium from activated carbon by contacting activated carbon adsorbed with technetium with a solution containing thiocyanate ions or iodine ions.
（実施例）
本発明を実施例についてさらに具体的に説明する。しか
し、本発明は実施例によって限定されるものではない。(Example) The present invention will be described in more detail with reference to Examples. However, the present invention is not limited to the examples.
過テクネチウム酸イオンを含む０．５Ｍ硝酸溶液中に活
性炭を添加し、室温に１時間放置することによって活性
炭にテクネチウムを吸着させた後、テクネチウム吸着活
性炭を溶液から分離し、水洗した。ここで活性炭に吸着
させたテクネチウムの量は、最初に溶液中に加えた９５
′″Ｔｃの放射能量から、吸着後に溶液中に残った９５
′″Ｔｃの放射能量を差引くことによって求めた。この
ようにして調製したテクネチウム吸着活性炭約０．２５
ｇを２０ｍ１のバイアルビンに入れた後、溶出剤１０
ｍ１を添加した。この試料を２５℃に設定したエアバス
中に入れ、回転ローラー上で１時間攪拌した。試料を取
出して遠心分離機にかけた後、上澄液の１ｍｌをサンプ
リングし、″″Ｔｃの放射能量を測定することによって
、活性炭からのテクネチウムの溶出率（％）及び分配係
数（Ｋｄ）を求めた。ここでＫｄは次の式で表される。Activated carbon was added to a 0.5M nitric acid solution containing pertechnetate ions, and technetium was adsorbed onto the activated carbon by allowing it to stand at room temperature for 1 hour, and then the technetium-adsorbed activated carbon was separated from the solution and washed with water. Here, the amount of technetium adsorbed on activated carbon is 95
'''From the amount of radioactivity of Tc, it was determined that 95 remained in the solution after adsorption.
'''It was determined by subtracting the amount of radioactivity of Tc. Technetium adsorption activated carbon prepared in this way was approximately 0.25
g into a 20 ml vial, then add eluent 10
m1 was added. This sample was placed in an air bath set at 25°C and stirred on a rotating roller for 1 hour. After removing the sample and centrifuging it, sample 1 ml of the supernatant and measure the amount of radioactivity of "" Tc to determine the elution rate (%) and partition coefficient (Kd) of technetium from activated carbon. Ta. Here, Kd is expressed by the following formula.
活性炭中（７） ”′″Ｔｃ？Ｊ１度（ｐ Ｃｉ／ｇ
）溶出剤の濃度をＩＭとして、種々の試薬について求め
たテクネチウムの溶出率及び分配係数を表に示した。In activated carbon (7) “′”Tc? J1 degree (p Ci/g
) The elution rate and distribution coefficient of technetium determined for various reagents are shown in the table, with the concentration of the eluent being IM.
表から明らかなように、チオシアン酸イオン又はヨウ素
イオンを含む溶出剤の場合には、他の場合に比べて高い
溶出率が得られることがわかる。As is clear from the table, in the case of an eluent containing thiocyanate ion or iodine ion, a higher elution rate can be obtained than in other cases.
なお、テクネチウムの溶出率は、試薬の濃度を増加させ
ること、あるいは溶液の酸性度を変化させることで高く
することが可能であり、２ＭＫＳＣＮでｐＨが７以上の
溶液を使用した場合には、テクネチウムの溶出率が９４
％以上となった。１回のバッチ操作により同様の溶出率
を硝酸濃度を濃くすることで達成することは困難であり
、４Ｍ硝酸溶液の場合でもテクネチウムの溶出率は６０
％に過ぎなかった。Note that the elution rate of technetium can be increased by increasing the concentration of the reagent or changing the acidity of the solution. The elution rate of
% or more. It is difficult to achieve the same elution rate by increasing the concentration of nitric acid in a single batch operation, and even in the case of a 4M nitric acid solution, the elution rate of technetium is 60%.
It was only %.
このため、テクネチウムを吸着させた活性炭からテクネ
チウム溶出するためには、チオシアン酸イオン又はヨウ
素イオンを含む溶液を使用することが特に有効である。Therefore, it is particularly effective to use a solution containing thiocyanate ions or iodine ions in order to elute technetium from activated carbon that has adsorbed technetium.
Claims (1)
することを特徴とするテクネチウムを吸着させた活性炭
からのテクネチウムの溶出方法。A method for eluting technetium from activated carbon adsorbed with technetium, which comprises contacting with a solution containing thiocyanate ions or iodine ions.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63203765A JPH0254732A (en) | 1988-08-18 | 1988-08-18 | Method for eluting technetium from activated carbon |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63203765A JPH0254732A (en) | 1988-08-18 | 1988-08-18 | Method for eluting technetium from activated carbon |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0254732A true JPH0254732A (en) | 1990-02-23 |
Family
ID=16479451
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63203765A Pending JPH0254732A (en) | 1988-08-18 | 1988-08-18 | Method for eluting technetium from activated carbon |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0254732A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2010146722A1 (en) | 2009-06-19 | 2010-12-23 | 株式会社化研 | Method and system for concentrating radioactive technetium as raw material for radioactive drug and labeling compound therefor and collecting the same by elution |
| US20110250108A1 (en) * | 2010-04-09 | 2011-10-13 | Ut-Battelle, Llc | Advanced dry head-end reprocessing of light water reactor spent nuclear fuel |
| CN111500861A (en) * | 2020-04-01 | 2020-08-07 | 原子高科股份有限公司 | Method for extracting technetium from neutral molybdenum solution by using activated carbon fiber |
-
1988
- 1988-08-18 JP JP63203765A patent/JPH0254732A/en active Pending
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2010146722A1 (en) | 2009-06-19 | 2010-12-23 | 株式会社化研 | Method and system for concentrating radioactive technetium as raw material for radioactive drug and labeling compound therefor and collecting the same by elution |
| JP2011002370A (en) * | 2009-06-19 | 2011-01-06 | Kaken:Kk | Method and system for concentration and elution recovery of radioactive technetium as material for radiopharmaceutical medicine and labeled compound of the same |
| US9236153B2 (en) | 2009-06-19 | 2016-01-12 | Kaken Co., Ltd. | Method of recovering enriched radioactive technetium and system therefor |
| EP2444106A4 (en) * | 2009-06-19 | 2016-04-20 | Kaken Co Ltd | Method and system for concentrating radioactive technetium as raw material for radioactive drug and labeling compound therefor and collecting the same by elution |
| US20110250108A1 (en) * | 2010-04-09 | 2011-10-13 | Ut-Battelle, Llc | Advanced dry head-end reprocessing of light water reactor spent nuclear fuel |
| US8574523B2 (en) * | 2010-04-09 | 2013-11-05 | Ut-Battelle, Llc | Advanced dry head-end reprocessing of light water reactor spent nuclear fuel |
| US8747790B2 (en) | 2010-04-09 | 2014-06-10 | Ut-Battelle, Llc | Advanced dry head-end reprocessing of light water reactor spent nuclear fuel |
| CN111500861A (en) * | 2020-04-01 | 2020-08-07 | 原子高科股份有限公司 | Method for extracting technetium from neutral molybdenum solution by using activated carbon fiber |
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