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Production of 191Pt from an iridium target
https://repo.qst.go.jp/records/66974
https://repo.qst.go.jp/records/66974b63c606c-6a6c-4917-80a9-6d3b14ef4388
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-11-14 | |||||
| タイトル | ||||||
| タイトル | Production of 191Pt from an iridium target | |||||
| 言語 | ||||||
| 言語 | jpn | |||||
| 資源タイプ | ||||||
| 資源タイプ識別子 | http://purl.org/coar/resource_type/c_c94f | |||||
| 資源タイプ | conference object | |||||
| アクセス権 | ||||||
| アクセス権 | metadata only access | |||||
| アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
| 著者 |
尾幡, 穂乃香
× 尾幡, 穂乃香× 尾幡 穂乃香 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Objectives: Auger electrons with high LET (4–26 keV/μm) in a short range (2–500 nm), have the potential for Targeted Radionuclide Therapy (1). Auger-emitting platinum radionuclides (191, 193m, 195mPt) are one of the promising candidates for radio-theranostic application because of their preferable decay properties and general applicability of platinum drugs as an anticancer agent. However, the production of carrier-free 191, 193mPt from an iridium target using an accelerator have not been so far established in spite of their high yield. Therefore, in this study, we contrived a new method on the practical production of 191Pt from an iridium target. \nMethods: A mixture of iridium and sodium peroxide (molar ratio 1:2) was irradiated with a vertical beam in a Nb target vessel semi-sealed with Nb foil (Fig.1). The irradiated mixture, which had formed a fused salt due to the strong heating by irradiation, was dissolved in 6M HCl. Subsequently, PtCl62- was completely separated from IrCl62- by the following procedures; selective reduction of IrCl62- by acetaldoxime, solvent extraction with TBP for rough separation, and anion exchange chromatography with a QMA column for purification of 191Pt. A chemical form of the final 191Pt product was identified by HPLC analysis. \nResults: The Ir target irradiated together with Na2O2 was easily dissolved in HCl, which suggested that the alkali fusion of Ir successfully occurred during the irradiation, although the efficiency was varied in 40–60% due to the uncontrollable beam focusing in the vessel. Most of IrCl62- was selectively reduced by acetaldoxime, and therefore, PtCl62- was quantitatively extracted by TBP. PtCl62- stripped from TBP was further isolated from trace amounts of Ir through anion-exchange chromatography using a QMA column. The chemical yield of 191Pt was 72±5%, and the final production yield for 191Pt was 4.6±0.5 MBq/μA h (after irradiation). The chemical form of the obtained *Pt species was identified to be *PtCl62- (97%) after refinement (see in Fig.2-(a)), and *PtCl42- (95%) after reduction (see in Fig.2-(b)). Conclusions: Carrier-free 191Pt produced using a cyclotron was successfully separated from the most corrosion-resistant Ir target. 191PtIVCl62- and 191PtⅡCl42- was independently prepared with very high radiochemical purities. \nReferences: (1) Kassis, A.I. and Adelstein, J.A. (2005) J. Nucl. Med., 46, 4S–12S. |
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| 会議概要（会議名, 開催地, 会期, 主催者等） | ||||||
| 内容記述タイプ | Other | |||||
| 内容記述 | The 10th China-Japan-Korea Symposium on Radiopharmaceutical Sciences (CJKSRS 2018)でのポスター発表 | |||||
| 発表年月日 | ||||||
| 日付 | 2018-11-03 | |||||
| 日付タイプ | Issued | |||||
