JPH04326096A - Producing method of target body for particle accelerator and radioactive isotope - Google Patents
Producing method of target body for particle accelerator and radioactive isotopeInfo
- Publication number
- JPH04326096A JPH04326096A JP9687491A JP9687491A JPH04326096A JP H04326096 A JPH04326096 A JP H04326096A JP 9687491 A JP9687491 A JP 9687491A JP 9687491 A JP9687491 A JP 9687491A JP H04326096 A JPH04326096 A JP H04326096A
- Authority
- JP
- Japan
- Prior art keywords
- target
- target body
- silver
- particle accelerator
- copper
- 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
- 239000002245 particle Substances 0.000 title claims abstract description 11
- 230000002285 radioactive effect Effects 0.000 title description 8
- 238000000034 method Methods 0.000 title description 3
- BQCADISMDOOEFD-UHFFFAOYSA-N Silver Chemical compound [Ag] BQCADISMDOOEFD-UHFFFAOYSA-N 0.000 claims abstract description 21
- 229910052709 silver Inorganic materials 0.000 claims abstract description 20
- 239000004332 silver Substances 0.000 claims abstract description 20
- 229910052802 copper Inorganic materials 0.000 claims abstract description 18
- 239000010949 copper Substances 0.000 claims abstract description 18
- 238000007747 plating Methods 0.000 claims abstract description 18
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 claims abstract description 17
- 238000004519 manufacturing process Methods 0.000 claims description 7
- 239000002994 raw material Substances 0.000 claims description 6
- 238000011084 recovery Methods 0.000 abstract description 11
- 238000000926 separation method Methods 0.000 abstract description 8
- 239000000126 substance Substances 0.000 abstract description 5
- 239000007788 liquid Substances 0.000 abstract 1
- 238000006243 chemical reaction Methods 0.000 description 8
- 239000013077 target material Substances 0.000 description 5
- 239000002253 acid Substances 0.000 description 3
- 230000000052 comparative effect Effects 0.000 description 3
- 238000001816 cooling Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 150000007513 acids Chemical class 0.000 description 2
- -1 HCl) Chemical class 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 238000005342 ion exchange Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 238000007086 side reaction Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000000758 substrate Substances 0.000 description 1
- 239000013076 target substance Substances 0.000 description 1
- 229910052725 zinc Inorganic materials 0.000 description 1
Abstract
Description
【0001】0001
【産業上の利用分野】本発明はサイクロトロン等の粒子
加速器用ターゲット本体及び該ターゲット本体を用いる
放射性同位元素の製造方法に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a target body for a particle accelerator such as a cyclotron, and a method for producing radioisotopes using the target body.
【0002】0002
【従来の技術】従来、斯かるターゲット本体の素材とし
ては、エネルギー照射時に発生する熱を考慮し、冷却効
果を上げるため、熱伝導に優れた銅が多く使用されてい
る。而して、放射性同位元素の製造に際しては、一般に
はターゲットの冷却効率の点から銅板をターゲット本体
とし、その表面にターゲット物質をメッキして安定な金
属としたものが通常固体ターゲットとして用いられてい
る。BACKGROUND OF THE INVENTION Conventionally, copper, which has excellent thermal conductivity, has often been used as a material for such target bodies in order to increase the cooling effect in consideration of the heat generated during energy irradiation. Therefore, in the production of radioactive isotopes, from the point of view of target cooling efficiency, a copper plate is generally used as the target body, and a target material is plated on the surface to make it a stable metal, which is usually used as a solid target. There is.
【0003】0003
【発明が解決しようとする課題】放射性同位元素を高純
度かつ高収率で製造するために、多くの場合、濃縮同位
体がターゲット物質として使用される。然るとき、濃縮
同位体は、その製造に多大の労力と時間を必要とする結
果、価格が極めて高価なものである。そのため、ターゲ
ット物質に荷電粒子を照射し、目的の放射性同位元素を
分離した後に、濃縮同位体を化学的に分離・精製する回
収作業が必要となる。In order to produce radioactive isotopes with high purity and high yield, enriched isotopes are often used as target materials. However, since enriched isotopes require a great deal of labor and time to produce, they are extremely expensive. Therefore, after the target material is irradiated with charged particles and the target radioactive isotope is separated, recovery work is required to chemically separate and purify the enriched isotope.
【0004】然るところ、従来の如き銅製ターゲット本
体を用いた場合には、陽子との低エネルギー側での核反
応により、銅による65Cu(p,n)65Zn反応に
よって半減期244日と長く、しかもγ線放出エネルギ
ーが1115keV と高い65Znが生成するので、
濃縮同位体の回収作業上、大きな問題となっていた。However, when a conventional copper target body is used, the half-life is as long as 244 days due to the 65Cu(p,n)65Zn reaction caused by the copper due to the low energy nuclear reaction with protons. Moreover, since 65Zn with a high gamma ray emission energy of 1115 keV is generated,
This has been a major problem in the recovery of enriched isotopes.
【0005】特に、67Gaを製造する場合には、濃縮
同位体である68Zn中への65Znの混入が避けられ
ないところ、68Znと65Znの化学分離は事実上不
可能であり、放射性同位元素製造上大きな障害となって
いたのが実状であった。In particular, when producing 67Ga, the contamination of 65Zn into 68Zn, which is an enriched isotope, is unavoidable, and chemical separation of 68Zn and 65Zn is virtually impossible, making it difficult to produce radioactive isotopes. The reality was that this was a major obstacle.
【0006】そこで、本発明者は斯かる銅製ターゲット
本体がもたらす問題を解決すべく種々研究を重ねた結果
、ターゲット本体を銀製又は銀メッキ製とすれば、優れ
た熱伝導性によりターゲット本体の冷却効果を上げ得る
と共に、陽子との核反応によって長半減期の核種が生成
せず、しかも物理・化学的に安定(HCl などの酸に
よって溶解されない)であるため、核反応によって生成
した核種が酸によるターゲット本体処理の際に溶解され
ず、極めて工業的に有利に放射性同位元素を製造し得る
ことを見い出し、本発明を完成した。[0006] Therefore, the inventor of the present invention conducted various studies to solve the problems caused by such a copper target body, and found that if the target body is made of silver or silver plating, the target body can be cooled due to its excellent thermal conductivity. In addition to being effective, the nuclear reaction with protons does not produce long-half-life nuclides, and it is physically and chemically stable (not dissolved by acids such as HCl), so the nuclides produced by the nuclear reaction do not react with acids. The present invention has been completed based on the discovery that radioactive isotopes can be manufactured very industrially advantageously without being dissolved during treatment of the target body.
【0007】[0007]
【課題を解決するための手段】すなわち、本発明は銀製
又は銀メッキ製としたことを特徴とする粒子加速器用タ
ーゲット本体及び該ターゲット本体表面に目的とする放
射性同位元素に対応するターゲット原料をメッキして得
た粒子加速器用ターゲットを用いることを特徴とする放
射性同位元素の製造方法である。[Means for Solving the Problems] That is, the present invention provides a target body for a particle accelerator characterized by being made of silver or silver plating, and a target material corresponding to a target radioisotope plated on the surface of the target body. This is a method for producing a radioactive isotope, which is characterized by using a particle accelerator target obtained by the above method.
【0008】本発明に於てターゲット本体を銀メッキ製
として実施する場合、その基体は銅製、換言すれば銅製
基体の表面に銀メッキを施してターゲット本体とするの
が好ましい。ここに銀メッキ層の厚さとしては10〜2
0μm程度で十分である。In the present invention, when the target body is made of silver plating, it is preferable that the base body is made of copper, in other words, the surface of the copper base body is plated with silver to form the target body. Here, the thickness of the silver plating layer is 10 to 2
A thickness of about 0 μm is sufficient.
【0009】尚、本発明に於て、ターゲット本体を銀メ
ッキ製とした場合には、コストの面のみならず副反応に
よって生成する放射性核種の生成率の点で全てを銀製と
したターゲット本体に比し良い結果が得られる。[0009] In the present invention, when the target body is made of silver plating, it is preferable to use a target body made entirely of silver, not only in terms of cost but also in terms of the production rate of radionuclides produced by side reactions. Comparatively better results can be obtained.
【0010】本発明によれば、斯かる銀製又は銀メッキ
製ターゲット本体の表面に、目的とする放射性同位元素
に対応するターゲット原料をそれぞれメッキして得たタ
ーゲットを用いることにより、常法に従い各種の放射性
同位元素が製造される。According to the present invention, by using a target obtained by plating the surface of such a silver or silver-plated target body with a target raw material corresponding to the target radioisotope, various types of of radioisotopes are produced.
【0011】特に、上記の如き本発明ターゲット本体表
面に、ターゲット原料として68Znをメッキして得た
ターゲットを用いれば、67Gaを効率的に製造するこ
とができると共に、68Znを高収率で回収することが
できる。In particular, if a target obtained by plating 68Zn as a target raw material on the surface of the target main body of the present invention as described above is used, 67Ga can be efficiently produced and 68Zn can be recovered at a high yield. be able to.
【0012】また、同様に本発明ターゲット本体表面に
、ターゲット原料として112Cdをメッキして得たタ
ーゲットを用いれば、111Inを効率的に製造するこ
とができると共に、112Cdを高収率で回収すること
ができる。[0012] Similarly, by using a target obtained by plating 112Cd as a target raw material on the surface of the target body of the present invention, 111In can be efficiently produced and 112Cd can be recovered at a high yield. Can be done.
【0013】[0013]
【実施例】以下実施例及び比較例を挙げて本発明を更に
説明する。[Examples] The present invention will be further explained below with reference to Examples and Comparative Examples.
【0014】実施例1
銅製基体の表面に銀メッキ(厚さ約10μm)を施して
得たターゲット本体を使用し、その表面に68Znメッ
キを施して67Ga製造用ターゲットとし、常法に従い
約30MeV の陽子ビームで20時間照射した。照射
終了後、当該68Znターゲット物質をHCl によっ
て溶解せしめた後、当該溶液中から化学分離方法に従い
67Gaを分離・精製した。Example 1 A target body obtained by silver plating (thickness: about 10 μm) on the surface of a copper substrate was used, and the surface was plated with 68Zn to make a target for producing 67Ga. It was irradiated with a proton beam for 20 hours. After the irradiation, the 68Zn target material was dissolved with HCl, and 67Ga was separated and purified from the solution according to a chemical separation method.
【0015】67Gaの分離後の残液(68Zn回収用
溶液)中に含まれる65Znの放射能量は約5mCi/
ターゲット本体であった。因に、銀メッキ製ターゲット
本体を用いることにより、本実施例の場合理論的には6
5Znは含まれないが、濃縮同位体自体に含まれている
不純物の66Zn、64Znとの核反応によって65Z
nが若干生成するものの、後述の比較例から明らかな如
く、その生成量は従来の1/4〜1/5程度と極めて微
量であった。The amount of radioactivity of 65Zn contained in the residual solution after separation of 67Ga (68Zn recovery solution) is approximately 5 mCi/
It was the target itself. Incidentally, by using a silver-plated target body, theoretically in this example, 6
Although 5Zn is not included, 65Z is produced through a nuclear reaction with impurities 66Zn and 64Zn contained in the enriched isotope itself.
Although a small amount of n was produced, as is clear from the comparative example described later, the amount produced was extremely small, about 1/4 to 1/5 of the conventional amount.
【0016】また、銀メッキ層の存在によりターゲット
基体たる銅がHCl により溶解されない結果、68Z
n回収用溶液中には元素として、Znのみが含まれてい
るので、68Znを回収する際には化学分離操作を必要
とせず、極めて簡単に、かつ高収率で回収することがで
きた(回収率99.8%)。Furthermore, due to the presence of the silver plating layer, the copper serving as the target base is not dissolved by HCl, and as a result, the 68Z
Since the n-recovery solution contains only Zn as an element, no chemical separation operation was required to recover 68Zn, and it was possible to recover it extremely easily and with a high yield ( Recovery rate 99.8%).
【0017】尚、回収された68Znは67Ga製造用
ターゲットとして銀メッキ製ターゲット本体にメッキさ
れ再使用される。The recovered 68Zn is plated on a silver-plated target body and reused as a target for producing 67Ga.
【0018】比較例1
銅製ターゲット本体(銀メッキ処理なし)を使用した以
外は実施例1と同様にして67Gaを分離・精製した。Comparative Example 1 67Ga was separated and purified in the same manner as in Example 1 except that a copper target body (without silver plating) was used.
【0019】67Gaの分離後の残液(68Zn回収用
溶液)中に含まれる65Znの放射能量は約20mCi
/ターゲット本体であった。The amount of radioactivity of 65Zn contained in the residual solution after separation of 67Ga (68Zn recovery solution) is approximately 20 mCi.
/ It was the target itself.
【0020】また、68Zn回収溶液中には、68Zn
ターゲット物質をHCl によって溶解する際に、HC
l とターゲット本体である銅との化学反応の結果、6
8Znと同時に銅も溶解されるので、Cu、Znの2元
素が含まれているため、イオン交換分離により、68Z
nを回収した(回収率85〜95%)。[0020] Also, in the 68Zn recovery solution, 68Zn
When dissolving a target substance with HCl, HC
As a result of the chemical reaction between l and the target body copper, 6
Since copper is also dissolved at the same time as 8Zn, since it contains two elements, Cu and Zn, 68Z can be dissolved by ion exchange separation.
n was recovered (recovery rate 85-95%).
【0021】[0021]
【発明の効果】本発明によれば、ターゲット本体の冷却
効果に優れ、しかも陽子との核反応によって長半減期の
核種が生成せず、かつ核反応によって生成した核種が酸
によるターゲット本体処理の際に溶解されることがない
ので、高価な濃縮同位体を容易かつ高収率で回収し得、
工業的に極めて有利に放射性同位元素を製造することが
できる。Effects of the Invention According to the present invention, the cooling effect of the target body is excellent, and in addition, nuclides with a long half-life are not generated due to the nuclear reaction with protons, and the nuclides generated by the nuclear reaction cannot be treated with acid. Expensive concentrated isotopes can be recovered easily and in high yields because they are not dissolved during the process.
Radioactive isotopes can be produced industrially with great advantage.
Claims (4)
とする粒子加速器用ターゲット本体。1. A target body for a particle accelerator, characterized in that it is made of silver or silver plating.
に、目的とする放射性同位元素に対応するターゲット原
料をメッキして得た粒子加速器用ターゲットを用いるこ
とを特徴とする放射性同位元素の製造方法。2. A method for producing a radioisotope, comprising using a target for a particle accelerator obtained by plating a target raw material corresponding to a target radioisotope on the surface of the target body according to claim 1. .
ーゲット本体の表面に、ターゲット原料として68Zn
をメッキして得た粒子加速器用ターゲットを用いること
を特徴とする67Gaの製造方法。3. 68Zn as a target raw material is applied to the surface of a target body obtained by silver plating the surface of a copper base.
A method for producing 67Ga, characterized by using a particle accelerator target obtained by plating 67Ga.
ーゲット本体の表面に、ターゲット原料として112C
dをメッキして得た粒子加速器用ターゲットを用いるこ
とを特徴とする111Inの製造方法。4. 112C as a target raw material is applied to the surface of a target body obtained by silver plating the surface of a copper base.
A method for producing 111In, characterized by using a particle accelerator target obtained by plating 111In.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP9687491A JPH04326096A (en) | 1991-04-26 | 1991-04-26 | Producing method of target body for particle accelerator and radioactive isotope |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP9687491A JPH04326096A (en) | 1991-04-26 | 1991-04-26 | Producing method of target body for particle accelerator and radioactive isotope |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH04326096A true JPH04326096A (en) | 1992-11-16 |
Family
ID=14176573
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP9687491A Pending JPH04326096A (en) | 1991-04-26 | 1991-04-26 | Producing method of target body for particle accelerator and radioactive isotope |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH04326096A (en) |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007508531A (en) * | 2003-10-13 | 2007-04-05 | アクチニウム ファーマシューティカルズ,インコーポレイティド | Radium target and production method thereof |
JP2009007633A (en) * | 2007-06-28 | 2009-01-15 | Gyoseiin Genshino Iinkai Kakuno Kenkyusho | Method for recovering cadmium-112 isotope |
US8153087B2 (en) | 2006-09-08 | 2012-04-10 | Actinium Pharmaceuticals Inc. | Method for the purification of radium from different sources |
US8349391B2 (en) | 2004-05-05 | 2013-01-08 | Actinium Pharmaceuticals Inc. | Radium target and method for producing it |
JP2014115229A (en) * | 2012-12-11 | 2014-06-26 | Sumitomo Heavy Ind Ltd | Radioisotope refiner |
US9534277B1 (en) | 2006-02-21 | 2017-01-03 | Actinium Pharmaceuticals, Inc. | Method for purification of 225AC from irradiated 226RA-targets |
CN111133842A (en) * | 2017-07-31 | 2020-05-08 | 斯蒂芬·泽塞尔 | System, apparatus and method for producing gallium radioisotopes on a particle accelerator using a solid target, and Ga-68 compositions produced thereby |
-
1991
- 1991-04-26 JP JP9687491A patent/JPH04326096A/en active Pending
Cited By (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007508531A (en) * | 2003-10-13 | 2007-04-05 | アクチニウム ファーマシューティカルズ,インコーポレイティド | Radium target and production method thereof |
JP4690328B2 (en) * | 2003-10-13 | 2011-06-01 | アクチニウム ファーマシューティカルズ,インコーポレイティド | Radium target and production method thereof |
US8349391B2 (en) | 2004-05-05 | 2013-01-08 | Actinium Pharmaceuticals Inc. | Radium target and method for producing it |
US9534277B1 (en) | 2006-02-21 | 2017-01-03 | Actinium Pharmaceuticals, Inc. | Method for purification of 225AC from irradiated 226RA-targets |
US9790573B2 (en) | 2006-02-21 | 2017-10-17 | Actinium Pharmaceuticals Inc. | Method for purification of 225AC from irradiated 226RA-targets |
US8153087B2 (en) | 2006-09-08 | 2012-04-10 | Actinium Pharmaceuticals Inc. | Method for the purification of radium from different sources |
US8715598B2 (en) | 2006-09-08 | 2014-05-06 | Actinium Pharmaceuticals Inc. | Method for the purification of radium from different sources |
JP2009007633A (en) * | 2007-06-28 | 2009-01-15 | Gyoseiin Genshino Iinkai Kakuno Kenkyusho | Method for recovering cadmium-112 isotope |
JP2014115229A (en) * | 2012-12-11 | 2014-06-26 | Sumitomo Heavy Ind Ltd | Radioisotope refiner |
CN111133842A (en) * | 2017-07-31 | 2020-05-08 | 斯蒂芬·泽塞尔 | System, apparatus and method for producing gallium radioisotopes on a particle accelerator using a solid target, and Ga-68 compositions produced thereby |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US20030016775A1 (en) | Production of high specific activity copper-67 | |
US9058908B2 (en) | Method for producing actinium-225 and isotopes of radium and target for implementing same | |
US20060023829A1 (en) | Medical radioisotopes and methods for producing the same | |
KR102490805B1 (en) | A method for purifying a solution containing 226Ra, a method for producing a 226Ra target, and a method for producing 225Ac | |
AU2001251607B2 (en) | A method for isolating and purifying 90Y from 90strontium in multi-curie quantities | |
US7569192B2 (en) | System for recovery of daughter isotopes from a source material | |
JPH04326096A (en) | Producing method of target body for particle accelerator and radioactive isotope | |
AU2001251607A1 (en) | A method for isolating and purifying 90Y from 90strontium in multi-curie quantities | |
Kondo et al. | Cyclotron isotopes and radiopharmaceuticals—XXII. Improved targetry and radiochemistry for production of 123I and 124I | |
Cieszykowska et al. | Separation of Ytterbium from 177 Lu/Yb mixture by electrolytic reduction and amalgamation | |
US9102997B2 (en) | Method of purification for recycling of gallium-69 isotope | |
Madhusudhan et al. | Cyclotron isotopes and radiopharmaceuticals XXXI. Improvements in 77 Br production and radiochemical separation from enriched 78 Se+ | |
CN113470843A (en) | Method for producing radioactive isotope | |
US8802041B1 (en) | Decontamination of radioactive metals | |
Das et al. | A cation exchange method for separation of 111In from inactive silver, copper, traces of iron and radioactive gallium and zinc isotopes | |
US2887358A (en) | Large scale method for the production and purification of curium | |
US3519385A (en) | Method for separating molybdenum from technetium | |
US5966583A (en) | Recovery of strontium activity from a strontium-82/rubidium-82 generator | |
US3573165A (en) | Production of high purity nickel-66 | |
JPH01102397A (en) | Manufacture of carrier free radioactive isotope yttrium-88 | |
US5482687A (en) | Separation of sodium-22 from irradiated targets | |
Duffield et al. | Preparation of High Specific Induced Radioactivity by Neutron Bombardment of Metal Chelate Compounds | |
US5487880A (en) | Production of sodium-22 from proton irradiated aluminum | |
RU2102125C1 (en) | Method of recovering from metals radioactive isotopes formed in nuclear transformation | |
RU2084980C1 (en) | Method for separating product radioactive nuclide from parent one |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
A02 | Decision of refusal |
Free format text: JAPANESE INTERMEDIATE CODE: A02 Effective date: 19990223 |