Simple and Feasible Method for 67Ga Production on CS-30 Cyclotron With High Purity
67Ga is a classical single photon imaging nuclide, which also has therapeutic potential due to its simultaneous emission of auger electrons. At present, 67Ga is mainly prepared by enrichment of Zn target. 67Ga can also be obtained by natZn(p, xn)67Ga nuclear reaction, but the existing separation met...
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Editorial Office of Journal of Nuclear and Radiochemistry
2025-04-01
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| Series: | He huaxue yu fangshe huaxue |
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| author | Han WU Ling-ting XIA Wen-liang LI Tian-zhen YE Long QIU Fei-ze LI Tu LAN Ji-jun YANG Jia-li LIAO Yuan-you YANG Ning LIU |
| author_facet | Han WU Ling-ting XIA Wen-liang LI Tian-zhen YE Long QIU Fei-ze LI Tu LAN Ji-jun YANG Jia-li LIAO Yuan-you YANG Ning LIU |
| author_sort | Han WU |
| collection | DOAJ |
| description | 67Ga is a classical single photon imaging nuclide, which also has therapeutic potential due to its simultaneous emission of auger electrons. At present, 67Ga is mainly prepared by enrichment of Zn target. 67Ga can also be obtained by natZn(p, xn)67Ga nuclear reaction, but the existing separation methods and processes need to be further optimized. In this study, a simple and feasible method for the preparation of high radionuclidic purity 67Ga from natural zinc target was studied. Zinc target with good quality was prepared by zinc sulfate system with target thickness ＞70 mg/cm2. To determine the best separation scheme of Ga, the simulated separation experiment of non-radioactive elements using 60% tributyl phosphate(TBP) resin was carried out. The distribution coefficients of Ga3+, Zn2+, Cu2+, Ni2+ and Co2+ ions in w=60% TBP resin under the action of 0.05, 0.10, 0.50, 1.00, 2.00, 4.00, 6.00 and 8.00 mol/L HCl were determined. We found that NH4Cl solution has good elution performance and can elute the adsorbed gallium. After eluting with 6.00 mol/L HCl, then eluted with 0.10, 0.30, 0.50, 0.75, 1.00 mol/L NH4Cl solution. The recovery of Ga was calculated respectively. According to the actual situation, the simulated solution was prepared and verified according to the experimental conditions obtained. 6.00 mol/L HCl and 0.50 mol/L NH4Cl were selected as the eluent. The results show that 60% TBP extraction resin has good separation effect. In order to verify the effectiveness of our separation method, a simulation separation experiment with trace amounts of radioactive Ga is conducted. The results of 68Ga tracer experiments are as good as those of non-radioactive experiments. The natural zinc target prepared by electroplating was bombarded with a beam of 21 MeV protons at 50 μA on the CS-30 cyclotron. The separation and purification process of high radionuclidic purity 67Ga from irradiated zinc target solution was established based on TBP extraction resin. According to the isotopic composition of zinc target material, the presence of trace amounts of 64Ga, 65Ga, 66Ga, 67Ga, 68Ga is estimated. However, after 5 days of decay, no short half-life nuclides(64Ga, 65Ga, 68Ga) have appeared, but a trace amount of 66Ga is still present in the product. The separation process is simple and efficient. The whole separation process can be completed within 2 hours. The radioactive recovery rate is greater than 90%. The radionuclidic purity is more than 99.9%. The yield of 67Ga obtained by natZn(p, xn)67Ga reaction is 13 MBq/(μA•h). This method also has reference value for the preparation of 68Ga by accelerator. |
| format | Article |
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| institution | DOAJ |
| issn | 0253-9950 |
| language | zho |
| publishDate | 2025-04-01 |
| publisher | Editorial Office of Journal of Nuclear and Radiochemistry |
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| series | He huaxue yu fangshe huaxue |
| spelling | doaj-art-b8e6bbb57bb942208ae061bce56d1c1c2025-08-20T03:14:19ZzhoEditorial Office of Journal of Nuclear and RadiochemistryHe huaxue yu fangshe huaxue0253-99502025-04-0147219019810.7538/hhx.2025.47.02.01902024-037Simple and Feasible Method for 67Ga Production on CS-30 Cyclotron With High PurityHan WU0Ling-ting XIA1Wen-liang LI2Tian-zhen YE3Long QIU4Fei-ze LI5Tu LAN6Ji-jun YANG7Jia-li LIAO8Yuan-you YANG9Ning LIU10Key Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, ChinaKey Laboratory of Radiation Physics and Technology of the Ministry of Education, Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064, China67Ga is a classical single photon imaging nuclide, which also has therapeutic potential due to its simultaneous emission of auger electrons. At present, 67Ga is mainly prepared by enrichment of Zn target. 67Ga can also be obtained by natZn(p, xn)67Ga nuclear reaction, but the existing separation methods and processes need to be further optimized. In this study, a simple and feasible method for the preparation of high radionuclidic purity 67Ga from natural zinc target was studied. Zinc target with good quality was prepared by zinc sulfate system with target thickness ＞70 mg/cm2. To determine the best separation scheme of Ga, the simulated separation experiment of non-radioactive elements using 60% tributyl phosphate(TBP) resin was carried out. The distribution coefficients of Ga3+, Zn2+, Cu2+, Ni2+ and Co2+ ions in w=60% TBP resin under the action of 0.05, 0.10, 0.50, 1.00, 2.00, 4.00, 6.00 and 8.00 mol/L HCl were determined. We found that NH4Cl solution has good elution performance and can elute the adsorbed gallium. After eluting with 6.00 mol/L HCl, then eluted with 0.10, 0.30, 0.50, 0.75, 1.00 mol/L NH4Cl solution. The recovery of Ga was calculated respectively. According to the actual situation, the simulated solution was prepared and verified according to the experimental conditions obtained. 6.00 mol/L HCl and 0.50 mol/L NH4Cl were selected as the eluent. The results show that 60% TBP extraction resin has good separation effect. In order to verify the effectiveness of our separation method, a simulation separation experiment with trace amounts of radioactive Ga is conducted. The results of 68Ga tracer experiments are as good as those of non-radioactive experiments. The natural zinc target prepared by electroplating was bombarded with a beam of 21 MeV protons at 50 μA on the CS-30 cyclotron. The separation and purification process of high radionuclidic purity 67Ga from irradiated zinc target solution was established based on TBP extraction resin. According to the isotopic composition of zinc target material, the presence of trace amounts of 64Ga, 65Ga, 66Ga, 67Ga, 68Ga is estimated. However, after 5 days of decay, no short half-life nuclides(64Ga, 65Ga, 68Ga) have appeared, but a trace amount of 66Ga is still present in the product. The separation process is simple and efficient. The whole separation process can be completed within 2 hours. The radioactive recovery rate is greater than 90%. The radionuclidic purity is more than 99.9%. The yield of 67Ga obtained by natZn(p, xn)67Ga reaction is 13 MBq/(μA•h). This method also has reference value for the preparation of 68Ga by accelerator.https://jnrc.xml-journal.net/cn/article/doi/10.7538/hhx.2025.47.02.0190zinc target67gaseparation |
| spellingShingle | Han WU Ling-ting XIA Wen-liang LI Tian-zhen YE Long QIU Fei-ze LI Tu LAN Ji-jun YANG Jia-li LIAO Yuan-you YANG Ning LIU Simple and Feasible Method for 67Ga Production on CS-30 Cyclotron With High Purity He huaxue yu fangshe huaxue zinc target 67ga separation |
| title | Simple and Feasible Method for 67Ga Production on CS-30 Cyclotron With High Purity |
| title_full | Simple and Feasible Method for 67Ga Production on CS-30 Cyclotron With High Purity |
| title_fullStr | Simple and Feasible Method for 67Ga Production on CS-30 Cyclotron With High Purity |
| title_full_unstemmed | Simple and Feasible Method for 67Ga Production on CS-30 Cyclotron With High Purity |
| title_short | Simple and Feasible Method for 67Ga Production on CS-30 Cyclotron With High Purity |
| title_sort | simple and feasible method for 67ga production on cs 30 cyclotron with high purity |
| topic | zinc target 67ga separation |
| url | https://jnrc.xml-journal.net/cn/article/doi/10.7538/hhx.2025.47.02.0190 |
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