JP4571109B2 - Production process of radioisotope thallium-201 - Google Patents
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Description
本発明は、放射性同位元素タリウム−２０１の製造工程に関し、特に、急速に純度が比較的に高いタリウム−２０１液を分離できるものに関する。 The present invention relates to a process for producing the radioisotope thallium-201, and particularly relates to a process capable of rapidly separating a thallium-201 liquid having a relatively high purity.
タリウム−２０１塩化第一タリウム（２０１ＴｌＣｌ２）が心筋に急速的に吸収されて心筋に集中されるため、心臓病気を診断するための心筋造影に利用され、また、腫瘤造影等の他の医療診断にも利用され、そのため、タリウム−２０１は海内外の核医学に利用される量がもっとも多い放射性同位元素の一つである。 Since thallium -201 thallous chloride (201 TlCl 2) is concentrated are rapidly absorbed into the myocardium myocardium is used to myocardial imaging for the diagnosis of cardiac disease, also mass other medical imaging such as It is also used for diagnosis, so thallium-201 is one of the most radioactive isotopes used in nuclear medicine in and out of the sea.
一般のタリウム−２０１の製造は、例えば、文献「Ｑａｉｍ Ｓ．Ｍ．、Ｗｅｉｎｒｅｉｃｈ Ｒ． ａｎｄ Ｏｌｌｉｇ Ｈ．、Ｐｒｏｄｕｃｔｉｏｎ ｏｆ Ｔｌ−２０１ ａｎｄ Ｐｂ２０３ ｖｉａ Ｐｒｏｔｏｎ Ｉｎｄｕｃｅｄ Ｎｕｃｌｅａｒ Ｒｅａｃｔｉｏｎ ｏｎ Ｎａｔｕｒａｌ Ｔｈａｌｌｉｕｍ、 Ｉｎｔｅｒｎａｔｉｏｎａｌ Ｊｏｕｒｎａｌ ｏｆ Ａｐｐｌｉｅｄ Ｒａｄｉａｔｉｏｎ ａｎｄ Ｉｓｏｔｏｐｅｓ、３０（１９７９）ｐｐ．８５−９５．」に掲示されているように、直接に清洗方式によりタリウム−２０１を洗出するものがある。しかしながら、清洗方式によりタリウム−２０１を洗出する時、タリウム−２０１に不純物が存在するため、製造したタリウム−２０１の純度が比較的に低く、実用的とは言えない。 Production of general thallium-201 is described in, for example, the literature “Qaim SM, Weinreich R. and Olig H., Production of Tl-201 and Pb203 via Protonal Induced Natural Reaction on Natural Tal. , 30 (1979) pp. 85-95., There are those that directly wash thallium-201 by a cleaning method . However, when thallium-201 is washed out by the cleansing method, impurities are present in thallium-201, so that the purity of the manufactured thallium-201 is relatively low, which is not practical.
本発明の主な目的は、タリウム−２０３をメッキ過程を介してタリウム−２０３固体ターゲット材料に形成して、陽子線を照射した後、第１、２の階段の化学分離ステップを介して、急速に純度が比較的に高いタリウム−２０１液体を分離できる放射性同位元素タリウム−２０１の製造工程を提供するにある。 The main purpose of the present invention, a thallium -203 forming the thallium -203 solid target material through a plating process, after irradiation with proton beam, through chemical separation step of the first and second stairs rapidly The present invention provides a process for producing the radioisotope thallium-201 capable of separating a thallium-201 liquid having a relatively high purity.
本発明は、上記の目的を達成するために、タリウム−２０３をメッキ過程を介してメッキターゲット材料に形成して、タリウム−２０３固体ターゲット材料とし、また、タリウム−２０３固体ターゲット材料に対してサイクロトロンで陽子線を照射し、そして、タリウム−２０３固体ターゲット材料を、硝酸と第二鉄の溶液（ＨＮＯ ３ ／Ｆｅ ３ ／Ｈ ２ Ｏ）から成る強酸液体で鉛−２０１とタリウム−２０３の溶液に溶解してから、アンモニア（ＮＨ３）と水を添加してタリウム−２０１と鉛−２０１の液体に共沈分離し、そして、塩酸（ＨＣｌ）を添加して樹脂でイオン交換を行い、鉛−２０１液体から不純物を濾過分離する第１段階の化学分離を行い、また、鉛−２０１液体を取り出してタリウム−２０１液体に変換させ、最後に、第２段階の化学分離を行うため、タリウム−２０１液体に二酸化硫黄を含有する塩酸ＨＣｌ（ＳＯ２）を添加し、樹脂で２次イオン交換を行い、純度が比較的に高いタリウム−２０１液を分離できる放射性同位元素タリウム−２０１の製造工程である。 In order to achieve the above object, the present invention forms thallium-203 on a plating target material through a plating process to form a thallium-203 solid target material, and a cyclotron for the thallium-203 solid target material. And the thallium-203 solid target material is made into a solution of lead-201 and thallium-203 with a strong acid liquid composed of nitric acid and ferric solution (HNO 3 / Fe 3 / H 2 O). After dissolution, ammonia (NH 3 ) and water are added to coprecipitate and separate into a liquid of thallium-201 and lead-201, and hydrochloric acid (HCl) is added to perform ion exchange with a resin. impurities from 201 liquid subjected to chemical separation of the first stage of filtration separation, also be converted is taken out of lead -201 liquid thallium -201 liquid, finally, To perform chemical separation of the two phases, addition of hydrochloric acid HCl (SO 2) to sulfur dioxide in the Thallium -201 Liquid performs secondary ion exchange resin, separating the purity is relatively high thallium -201 solution It is a manufacturing process of radioisotope thallium-201 that can be produced.
図１は、本発明の基本流れのフロー概念図である。図のように、本発明は、放射性同位元素タリウム−２０１の製造工程であり、少なくとも、メッキステップ１と照射ステップ２、第１の階段の化学分離ステップ３、変換ステップ４及び第２の階段の化学分離ステップ５等が含有され、当該第１段階の化学分離ステップ３は、溶解ステップ３１と共沈ステップ３２及び１次イオン交換ステップ３３等のステップが含有され、当該第２段階の化学分離ステップ５は２次イオン交換ステップ５１であり、上記のステップにより、新規な放射性同位元素タリウム−２０１の製造工程が構成され、急速に純度が比較的に高いタリウム−２０１液体を濾過できる。 FIG. 1 is a conceptual flow diagram of the basic flow of the present invention. As shown in the figure, the present invention is a manufacturing process of the radioisotope thallium-201. At least the plating step 1 and the irradiation step 2, the chemical separation step 3 of the first step, the conversion step 4 and the second step. Chemical separation step 5 and the like are included, and the first stage chemical separation step 3 includes steps such as a dissolution step 31, a coprecipitation step 32, and a primary ion exchange step 33, and the second stage chemical separation step. Reference numeral 5 denotes a secondary ion exchange step 51. By the above steps, a manufacturing process of a novel radioisotope thallium-201 is configured, and a thallium-201 liquid having a relatively high purity can be rapidly filtered.
図２は、本発明に係わる製造形態の流れのフロー概念図である。図のように、本発明は、次の製造ステップが含有される。 FIG. 2 is a conceptual flow diagram of a manufacturing mode according to the present invention. As shown, the present invention includes the following manufacturing steps.
メッキステップ１は、タリウム−２０３（１１）をメッキ過程を介してメッキターゲット材料に形成して、タリウム−２０３固体ターゲット材料１２とする。 In the plating step 1, thallium-203 (11) is formed on a plating target material through a plating process to obtain a thallium-203 solid target material 12.
照射ステップ２は、タリウム−２０３固体ターゲット材料１２に対して、サイクロトロン２１で陽子線を照射し、また、当該サイクロトロン２１の照射エネルギーが、１５ＭｅＶ〜４０ＭｅＶの間である。 In the irradiation step 2, the thallium-203 solid target material 12 is irradiated with a proton beam by the cyclotron 21, and the irradiation energy of the cyclotron 21 is between 15 MeV and 40 MeV.
第１段階の化学分離ステップ３は、溶解ステップ３１と共沈ステップ３２及び１次イオン交換ステップ３３等のステップが含有される。 Chemical separation step 3 of the first stage, steps such as dissolution step 31 and coprecipitated step 32 and the primary ion exchange step 33 is contained.
溶解ステップ３１は、照射した後、強酸液体３４で当該タリウム−２０３固体ターゲット材料１２を溶解し、当該タリウム−２０３固体ターゲット材料１２を鉛−２０１溶液３５とタリウム−２０３溶液３６に形成し、当該強酸液体３４が硝酸と第二鉄の水溶液（ＨＮＯ３／Ｆｅ３／Ｈ２Ｏ）である。 In the dissolving step 31, after irradiation, the thallium-203 solid target material 12 is dissolved with a strong acid liquid 34 to form the thallium-203 solid target material 12 into a lead-201 solution 35 and a thallium-203 solution 36. The strong acid liquid 34 is an aqueous solution of nitric acid and ferric iron (HNO 3 / Fe 3 / H 2 O).
共沈ステップ３２は、更に、鉛−２０１溶液３５とタリウム−２０３溶液３６にアンモニア（ＮＨ３）と水３２１を添加して共沈させ、当該鉛−２０１溶液３５とタリウム−２０３溶液３６がタリウム−２０３液体３７と鉛−２０１液体３８に分離される。 In the coprecipitation step 32, ammonia (NH 3 ) and water 321 are further added to the lead-201 solution 35 and thallium-203 solution 36 for coprecipitation, and the lead-201 solution 35 and thallium-203 solution 36 are added to thallium. -Separated into 203 liquid 37 and lead-201 liquid 38.
１次イオン交換ステップ３３は、タリウム−２０３液体３７と鉛−２０１液体３８に塩酸（ＨＣｌ）３３１を添加し、樹脂３３２でイオン交換を行い、鉛−２０１液体３８から不純物を濾過分離する。 In the primary ion exchange step 33, hydrochloric acid (HCl) 331 is added to the thallium- 203 liquid 37 and the lead-201 liquid 38, ion exchange is performed with the resin 332, and impurities are separated from the lead-201 liquid 38 by filtration.
変換ステップ４は、更に、鉛−２０１液体３８を取り出して減衰させ、鉛−２０１液体３８をタリウム−２０１液体４１に変換させる。 In the conversion step 4, the lead-201 liquid 38 is further taken out and attenuated to convert the lead-201 liquid 38 into the thallium-201 liquid 41.
第２段階の化学分離ステップ５は、２次イオン交換ステップ５１であり、当該２次イオン交換ステップ５１は、更に、タリウム−２０１液体４１に二酸化硫黄を含有する塩酸ＨＣｌ（ＳＯ２）５１１を添加し、樹脂５１２でイオン交換を行い、純度が比較的に高いタリウム−２０１液体５２を濾過できる。 The second- stage chemical separation step 5 is a secondary ion exchange step 51, and the secondary ion exchange step 51 further adds hydrochloric acid HCl (SO 2 ) 511 containing sulfur dioxide to the thallium-201 liquid 41. Then, ion exchange is performed with the resin 512, and the thallium-201 liquid 52 having a relatively high purity can be filtered.
以上のように、本発明に係わる放射性同位元素タリウム−２０１の製造工程によれば、有効的に従来の各欠点を改善でき、タリウム−２０３をメッキ過程を介してタリウム−２０３固体ターゲット材料に形成し、陽子線を照射してから、第１、２段階の化学分離ステップを介して、急速に純度が比較的に高いタリウム−２０１液体を濾過できるため、本発明は、より進歩的且つ実用的であるため、法に従って特許出願する。 As described above, according to the manufacturing process of the radioisotope thallium-201 according to the present invention, the conventional defects can be effectively improved, and thallium-203 is formed on the thallium-203 solid target material through the plating process. and, after irradiation with proton beam, through chemical separation step of the first and second stage, rapidly since purity filterable high thallium -201 liquid relatively, the present invention is more advanced and practical Therefore, a patent application is filed according to the law.
以上は、ただ、本発明のより良い実施例であり、本発明に係わる特許請求の範囲は、それによって制限されず、また、本発明に係わる特許請求の範囲や明細書の内容に従って行う等価の変更や修正は、全てが、本発明に係わる特許請求の範囲内に含まれる。 The above are merely preferred embodiments of the present invention, and the scope of the claims related to the present invention is not limited thereby, and equivalent claims made according to the scope of the claims and the description of the present invention. All changes and modifications are included in the scope of the claims of the present invention.
１ メッキステップ
１１ タリウム−２０３
１２ タリウム−２０３固体ターゲット材料
２ 照射ステップ
２１ サイクロトロン
３ 第１の階段の化学分離ステップ
３１ 溶解ステップ
３２ 共沈ステップ
３２１ アンモニア（ＮＨ３）と水
３３ １次イオン交換ステップ
３３１ 塩酸
３３２ 樹脂
３４ 強酸液体
３５ 鉛−２０１溶液
３６ タリウム−２０３溶液
３７ タリウム−２０３液体
３８ 鉛−２０１液体
４ 変換ステップ
４１ タリウム−２０１液体
５ 第２の階段の化学分離ステップ
５１ ２次イオン交換ステップ
５１１ 二酸化硫黄を有する塩酸ＨＣｌ（ＳＯ２）
５１２ 樹脂
５２ タリウム−２０１液体
1 plating step 11 thallium-203
12 Thallium-203 solid target material 2 Irradiation step 21 Cyclotron 3 First step chemical separation step 31 Dissolution step 32 Coprecipitation step 321 Ammonia (NH 3 ) and water 33 Primary ion exchange step 331 Hydrochloric acid 332 Resin 34 Strong acid liquid 35 Lead-201 solution 36 thallium-203 solution 37 thallium- 203 liquid 38 lead-201 liquid 4 conversion step 41 thallium-201 liquid 5 second step chemical separation step 51 secondary ion exchange step 511 HCl HCl with sulfur dioxide ( SO 2)
512 resin 52 thallium-201 liquid
Claims (4)
タリウム−２０３をメッキ過程を介してメッキターゲット材料に形成して、タリウム−２０３固体ターゲット材料とするメッキステップと、
タリウム−２０３固体ターゲット材料に対してサイクロトロンで陽子線を照射する照射ステップと、
タリウム−２０３固体ターゲット材料を、硝酸と第二鉄の溶液（ＨＮＯ ３ ／Ｆｅ ３ ／Ｈ ２ Ｏ）から成る強酸液体で鉛−２０１とタリウム−２０３の溶液に溶解してから、アンモニア（ＮＨ３）と水を添加してタリウム−２０３と鉛−２０１の液体に共沈分離し、そして、塩酸（ＨＣｌ）を添加して樹脂でイオン交換を行い、鉛−２０１液体から不純物を濾過分離する第１段階の化学分離ステップと、
鉛−２０１液体を取り出して減衰させ、鉛−２０１液体をタリウム−２０１液体に変換させる変換ステップと、
タリウム−２０１液体に二酸化硫黄を含有する塩酸ＨＣｌ（ＳＯ２）を添加し、樹脂で２次イオン交換を行って、純度が比較的に高いタリウム−２０１液体を濾過する第２段階の化学分離ステップと、
が含有される、
ことを特徴とする放射性同位元素タリウム−２０１の製造工程。 at least,
Forming a thallium-203 on a plating target material through a plating process to form a thallium-203 solid target material;
An irradiation step of irradiating a thallium- 203 solid target material with a proton beam with a cyclotron;
A thallium-203 solid target material is dissolved in a solution of lead-201 and thallium-203 with a strong acid liquid consisting of a solution of nitric acid and ferric iron (HNO 3 / Fe 3 / H 2 O) , and then ammonia (NH 3 ) And water are added to coprecipitate and separate into thallium- 203 and lead-201 liquids, and hydrochloric acid (HCl) is added to perform ion exchange with the resin, and impurities are filtered and separated from the lead-201 liquid. A one- step chemical separation step;
A conversion step of removing the lead-201 liquid and attenuating it to convert the lead-201 liquid into a thallium-201 liquid;
Hydrochloric acid was added HCl (SO 2) to sulfur dioxide in the Thallium -201 liquid by performing secondary ion exchange resin, chemical separation step of the second stage of filtering the purity is relatively high thallium -201 Liquid When,
Contains,
The manufacturing process of the radioisotope thallium-201 characterized by the above-mentioned.
タリウム−２０３をメッキ過程を介してメッキターゲット材料に形成して、タリウム−２０３固体ターゲット材料とするメッキステップと、
タリウム−２０３固体ターゲット材料に対して、サイクロトロンで陽子線を照射する照射ステップと、
照射した後、硝酸と第二鉄の溶液（ＨＮＯ ３ ／Ｆｅ ３ ／Ｈ ２ Ｏ）から成る強酸液体で当該タリウム−２０３固体ターゲット材料を溶解し、当該タリウム−２０３固体ターゲット材料を鉛−２０１とタリウム−２０３の溶液に形成する溶解ステップと、
鉛−２０１とタリウム−２０３の溶液にアンモニア（ＮＨ３）と水を添加して共沈し、当該鉛−２０１とタリウム−２０３の溶液がタリウム−２０３と鉛−２０１の液体に分離される共沈ステップと、
タリウム−２０３と鉛−２０１の液体に塩酸（ＨＣｌ）を添加して樹脂でイオン交換を行い、鉛−２０１液体から不純物を濾過分離する１次イオン交換ステップと、
鉛−２０１液体を取り出して減衰させ、鉛−２０１液体をタリウム−２０１液体に変換させる変換ステップと、
タリウム−２０１液体に二酸化硫黄を含有する塩酸ＨＣｌ（ＳＯ２）を添加し、樹脂でイオン交換を行い、純度が比較的に高いタリウム−２０１液体を分離する２次イオン交換ステップと、
が含有される、
ことを特徴とする放射性同位元素タリウム−２０１の製造工程。 at least,
Forming a thallium-203 on a plating target material through a plating process to form a thallium-203 solid target material;
An irradiation step of irradiating the thallium-203 solid target material with a proton beam with a cyclotron;
After irradiation, the thallium-203 solid target material is dissolved with a strong acid liquid composed of a solution of nitric acid and ferric iron (HNO 3 / Fe 3 / H 2 O) , and the thallium-203 solid target material is converted to lead-201. A dissolution step to form a solution of thallium-203;
Co-precipitation is performed by adding ammonia (NH 3 ) and water to a solution of lead-201 and thallium-203, and the solution of lead-201 and thallium-203 is separated into a liquid of thallium- 203 and lead-201. Settling step,
A primary ion exchange step of adding hydrochloric acid (HCl) to the thallium- 203 and lead-201 liquid, performing ion exchange with the resin, and filtering and separating impurities from the lead-201 liquid;
A conversion step of removing the lead-201 liquid and attenuating it to convert the lead-201 liquid into a thallium-201 liquid;
Hydrochloric acid was added HCl (SO 2) to sulfur dioxide in the Thallium -201 liquid, ion exchange resin, and secondary ion exchange step of separating the purity is relatively high thallium -201 liquid,
Contains,
The manufacturing process of the radioisotope thallium-201 characterized by the above-mentioned.
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| JPH01102397A (en) * | 1987-10-16 | 1989-04-20 | Nippon Telegr & Teleph Corp <Ntt> | Manufacture of carrier free radioactive isotope yttrium-88 |
| JP2004535288A (en) * | 2001-06-05 | 2004-11-25 | メジ − フィジックス、インコーポレイテッド | Target processing |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| US3993538A (en) * | 1976-01-27 | 1976-11-23 | The United States Of America As Represented By The United States Energy Research And Development Administration | Production of high purity radiothallium |
| JPH01102397A (en) * | 1987-10-16 | 1989-04-20 | Nippon Telegr & Teleph Corp <Ntt> | Manufacture of carrier free radioactive isotope yttrium-88 |
| JP2004535288A (en) * | 2001-06-05 | 2004-11-25 | メジ − フィジックス、インコーポレイテッド | Target processing |
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