JP2008104988A - Separation apparatus for radioisotope thallium-201 - Google Patents
Separation apparatus for radioisotope thallium-201 Download PDFInfo
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Abstract
Description
本発明は、放射性同位元素タリウム−２０１の分離装置に関し、特に、迅速に純度が比較的に高い鉛−２０１液体を分離でき、そして、当該鉛−２０１液体に対して、減衰とイオン交換を行って放射性同位元素タリウム−２０１が得られる分離装置に関する。 The present invention relates to an apparatus for separating radioisotope thallium-201, and in particular, can quickly separate a lead-201 liquid having a relatively high purity, and performs attenuation and ion exchange on the lead-201 liquid. The present invention relates to a separation apparatus from which radioisotope thallium-201 is obtained.
タリウム−２０１塩化第一タリウムは、心筋によって素早く吸収されて心筋に集中するため、心臓病を診断するための心筋造影に利用され、また、腫瘍造影等の他の医療診断に利用され、そのため、タリウム−２０１は、内外の核医学分野において、使用量が最も多い放射性同位元素の一つである。 Thallium-201 thallium chloride is quickly absorbed by the myocardium and concentrated in the myocardium, so it is used for myocardial imaging for diagnosing heart disease, and for other medical diagnoses such as tumor imaging, Thallium-201 is one of the most used radioisotopes in the field of nuclear medicine inside and outside.
一般の、タリウム−２０１の製造方法は、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．」に記載されているように、直接的に清水洗によりタリウム−２０１を洗い出す。しかし、清水洗によってタリウム−２０１を洗い出す時、タリウム−２０１に不純物が存在するため、作造されたタリウム−２０１の純度が比較的に低いから、実用的とは言えない。 The general method for producing thallium-201 is described in 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., Thallium-201 is washed out directly by washing with fresh water. However, when thallium-201 is washed out by washing with fresh water, impurities are present in thallium-201, so that the produced thallium-201 has a relatively low purity, so it is not practical.
本発明の主な目的は、タリウム−２０３固体ターゲット材料から迅速に鉛−２０１液体を分離でき、そして、鉛−２０１液体に対して減衰とイオン交換を行って放射性同位元素タリウム−２０１が得られる放射性同位元素タリウム−２０１の分離装置を提供する。 The main object of the present invention is to quickly separate lead-201 liquid from thallium-203 solid target material and to attenuate and ion exchange the lead-201 liquid to obtain the radioisotope thallium-201. An apparatus for separating the radioisotope thallium-201 is provided.
本発明は、上記の目的を達成するために、少なくとも、溶解槽と、第１の制御弁と第２の制御弁及び第３の制御弁が連接される真空装置と、第４の制御弁が連接される第１のガラス槽と、三方制御弁が連接される共沈槽と、第５の制御弁が連接される第２のガラス槽と、第６の制御弁が連接されるイオン交換柱と、鉛−２０１収集瓶と、第７の制御弁が連接される第３のガラス槽と、タリウム−２０３収集瓶と、から構成される放射性同位元素タリウム−２０１の分離装置である。 In order to achieve the above object, the present invention includes at least a dissolution tank, a vacuum device in which a first control valve, a second control valve, and a third control valve are connected, and a fourth control valve. The first glass tank connected, the coprecipitation tank connected with the three-way control valve, the second glass tank connected with the fifth control valve, and the ion exchange column connected with the sixth control valve. And a lead-201 collection bottle, a third glass tank to which a seventh control valve is connected, and a thallium-203 collection bottle.
図１は、本発明の基本構造概念図である。図のように、本発明は、放射性同位元素タリウム−２０１の分離装置であり、少なくとも、溶解槽１と、第１の制御弁２１と第２の制御弁２２及び第３の制御弁２３が連接される真空装置２と、一側に第４の制御弁３１が連接され、もう一側に第１の制御弁２１が連接される第１のガラス槽３と、三方制御弁４１が連接される共沈槽４と、一側に第５の制御弁５１が連接され、もう一側に第２の制御弁２２が連接される第２のガラス槽５と、一側に第６の制御弁６１が連接され、もう一側に第５の制御弁５１が連接されるイオン交換柱６と、鉛−２０１収集瓶７と、一側に第７の制御弁８１が連接され、もう一側に第３の制御弁２３が連接される第３のガラス槽８と、タリウム−２０３収集瓶９と、から構成され、当該三方制御弁４１は、第８の制御弁４２が連接され、上記の構造により、快速的に鉛−２０１液体を分離できる新規な放射性同位元素タリウム−２０１の分離装置が構成される。 FIG. 1 is a conceptual diagram of the basic structure of the present invention. As shown in the figure, the present invention is a separation apparatus for radioisotope thallium-201, and at least a dissolution tank 1, a first control valve 21, a second control valve 22, and a third control valve 23 are connected. The vacuum control device 2 is connected to the fourth control valve 31 on one side, the first glass tank 3 is connected to the first control valve 21 on the other side, and the three-way control valve 41 is connected. The coprecipitation tank 4 is connected to the fifth control valve 51 on one side, the second glass tank 5 is connected to the second control valve 22 on the other side, and the sixth control valve 61 is on the one side. Are connected, the ion control column 6 is connected to the fifth control valve 51 on the other side, the lead-201 collection bottle 7, the seventh control valve 81 is connected to the one side, and the second control valve 81 is connected to the other side. 3 control valve 23 is connected to a third glass tank 8 and a thallium-203 collection bottle 9. A control valve 42 is connected, by the structure described above, the separating apparatus of a novel radioisotope thallium -201 is configured capable of fast isolated lead -201 liquid.
図２は、本発明の一実施例の概念図である。図のように、本発明に係わる分離装置により、タリウム−２０３固体ターゲット材料を分離して、鉛−２０１液体が分離され、また、当該鉛−２０１液体に対して衰退とイオン交換を行うことにより、放射性同位元素タリウム−２０１が得られる。 FIG. 2 is a conceptual diagram of an embodiment of the present invention. As shown in the figure, the separation apparatus according to the present invention separates the thallium-203 solid target material to separate the lead-201 liquid, and the lead-201 liquid is subjected to decay and ion exchange. The radioisotope thallium-201 is obtained.
操作に際して、まず、鉛−２０１を含有するタリウム−２０３固体ターゲット材料を当該溶解槽１に入れ込んでから、１．６Ｎ硝酸と第二鉄イオン及び注射用水を添加し、当該タリウム−２０３固体ターゲット材料が溶液に溶解される。 In operation, first, thallium-203 solid target material containing lead-201 is put into the dissolution tank 1, 1.6N nitric acid, ferric ion and water for injection are added, and the thallium-203 solid target is added. The material is dissolved in the solution.
第１の制御弁２１を開放して、当該真空装置２により全部の鉛−２０１溶液とタリウム−２０３溶液を当該第１のガラス槽３に吸い込み、その後、当該第１の制御弁２１を締めてから、アンモニアを添加して混合し、そして、第４の制御弁３１を開放して、当該第１のガラス槽３内においてアンモニアと混合した鉛−２０１溶液とタリウム−２０３溶液が当該共沈槽４に滴入し、そして、水を添加して共沈させ、これにより、当該鉛−２０１溶液とタリウム−２０３溶液が、タリウム−２０３液体と鉛−２０１液体に分離される。 The first control valve 21 is opened, all the lead-201 solution and the thallium-203 solution are sucked into the first glass tank 3 by the vacuum device 2, and then the first control valve 21 is closed. Then, ammonia is added and mixed, and the fourth control valve 31 is opened, and the lead-201 solution and the thallium-203 solution mixed with ammonia in the first glass tank 3 are the coprecipitation tank. 4 and then co-precipitated by adding water, whereby the lead-201 solution and thallium-203 solution are separated into thallium-203 liquid and lead-201 liquid.
第２の制御弁２２を開放して、真空装置２により、当該共沈槽４から、全部の鉛−２０１液体を第２のガラス槽５内に吸い込み、その後、当該第２の制御弁２２を締めてから、８Ｎ塩酸を添加して混合し、そして、第５の制御弁５１を開放して、当該鉛−２０１液体が当該イオン交換柱６に滴入し、そして、樹脂によりイオン交換を行い、これにより、鉛−２０１液体中の鉄を濾過分離し、続いて、第６の制御弁６１を開放し、純粋な鉛−２０１液体が鉛−２０１収集瓶７に滴入する。 The second control valve 22 is opened, and the vacuum apparatus 2 sucks all lead-201 liquid from the coprecipitation tank 4 into the second glass tank 5, and then the second control valve 22 is turned on. After tightening, 8N hydrochloric acid is added and mixed, then the fifth control valve 51 is opened, the lead-201 liquid drops into the ion exchange column 6, and ion exchange is performed with resin. Thereby, the iron in the lead-201 liquid is separated by filtration, and then the sixth control valve 61 is opened, and the pure lead-201 liquid drops into the lead-201 collection bottle 7.
そして、共沈槽４に連接される三方制御弁４１と第３の制御弁２３を開放し、真空装置２により、当該共沈槽４にあるタリウム−２０３液体を、当該第３のガラス槽８に吸い込んでから、当該第３の制御弁２３を締めるとともに第７の制御弁８１を開放し、これにより、当該第３のガラス槽８内のタリウム−２０３液体が、当該タリウム−２０３収集瓶９に滴入する。 Then, the three-way control valve 41 and the third control valve 23 connected to the coprecipitation tank 4 are opened, and the thallium-203 liquid in the coprecipitation tank 4 is transferred to the third glass tank 8 by the vacuum device 2. Then, the third control valve 23 is tightened and the seventh control valve 81 is opened, so that the thallium-203 liquid in the third glass tank 8 is transferred to the thallium-203 collection bottle 9. Drip into.
その後、鉛−２０１収集瓶７から鉛−２０１液体を取り出して減衰させ、鉛−２０１液体が、タリウム−２０１液体に減衰されてから、イオン交換により、放射性同位元素タリウム−２０１が得られる。また、当該三方制御弁４１は、第８の制御弁４２が連接され、窒素ガスの供給を制御できる。 Thereafter, the lead-201 liquid is taken out from the lead-201 collection bottle 7 and attenuated. After the lead-201 liquid is attenuated to the thallium-201 liquid, the radioisotope thallium-201 is obtained by ion exchange. The three-way control valve 41 is connected to an eighth control valve 42 and can control the supply of nitrogen gas.
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の分離装置は、有効的に従来の様々の欠点を改善でき、迅速にタリウム−２０３固体ターゲット材料から鉛−２０１液体が分離され、そして、当該鉛−２０１液体に対して減衰とイオン交換を行うことにより、放射性同位元素タリウム−２０１が得られ、そのため、本発明は、より実用的なものであるから、法に従って特許出願する。 As described above, the apparatus for separating radioisotope thallium-201 according to the present invention can effectively improve various conventional drawbacks, and lead-201 liquid can be quickly separated from thallium-203 solid target material, and By subjecting the lead-201 liquid to attenuation and ion exchange, the radioisotope thallium-201 is obtained. Therefore, the present invention is more practical, so 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、本発明は、それによって制限されることがなく、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った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 present invention is not limited thereby, and equivalent changes and modifications made in accordance with the scope of the claims and the description of the present invention are not limited thereto. All within the scope of the claims relating to the present invention.
１ 溶解槽
２ 真空装置
２１ 第１の制御弁
２２ 第２の制御弁
２３ 第３の制御弁
３ 第１のガラス槽
３１ 第４の制御弁
４ 共沈槽
４１ 三方制御弁
４２ 第８の制御弁
５ 第２のガラス槽
５１ 第５の制御弁
６ イオン交換柱
６１ 第６の制御弁
７ 鉛−２０１収集瓶
８ 第３のガラス槽
８１ 第７の制御弁
９ タリウム−２０１収集瓶
DESCRIPTION OF SYMBOLS 1 Dissolution tank 2 Vacuum device 21 1st control valve 22 2nd control valve 23 3rd control valve 3 1st glass tank 31 4th control valve 4 Coprecipitation tank 41 Three-way control valve 42 8th control valve 5 Second glass tank 51 Fifth control valve 6 Ion exchange column 61 Sixth control valve 7 Lead-201 collection bottle 8 Third glass tank 81 Seventh control valve 9 Thallium-201 collection bottle
Claims (2)
一側に第４の制御弁が連接され、もう一側に当該第１の制御弁が連接される第１のガラス槽と、
三方制御弁が連接される共沈槽と、
一側に第５の制御弁が連接され、もう一側に当該第２の制御弁が連接される第２のガラス槽と、
一側に当該第５の制御弁が連接され、もう一側に第６の制御弁が連接されるイオン交換柱と、
鉛−２０１収集瓶と、
一側に第７の制御弁が連接され、もう一側に当該第３の制御弁が連接される第３のガラス槽と、
タリウム−２０３収集瓶と、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の分離装置。 At least a dissolution tank, and a vacuum device connected to the first control valve, the second control valve, and the third control valve, respectively,
A first glass tank having a fourth control valve connected to one side and the first control valve connected to the other side;
A co-precipitation tank connected with a three-way control valve;
A second glass tank having a fifth control valve connected to one side and the second control valve connected to the other side;
An ion exchange column having the fifth control valve connected to one side and the sixth control valve connected to the other side;
A lead-201 collection bottle;
A third glass tank having a seventh control valve connected to one side and the third control valve connected to the other side;
An apparatus for separating radioisotope thallium-201, comprising: a thallium-203 collection bottle.
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| JP2006292079A JP4674727B2 (en) | 2006-10-27 | 2006-10-27 | Separation apparatus for radioisotope thallium-201 |
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| JP2006292079A JP4674727B2 (en) | 2006-10-27 | 2006-10-27 | Separation apparatus for radioisotope thallium-201 |
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| JP2008104988A true JP2008104988A (en) | 2008-05-08 |
| JP4674727B2 JP4674727B2 (en) | 2011-04-20 |
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Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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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2006
- 2006-10-27 JP JP2006292079A patent/JP4674727B2/en not_active Expired - Fee Related
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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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| JP4674727B2 (en) | 2011-04-20 |
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