С. Д. Бринкевич, Д. И. Бринкевич, А. И. Киевицкая, А. Н. Кийко, И. А. Ковалёв, Sviatoslav D . Brinkevich, D. Brinkevich, H. I. Kiyavitskaya, Aliaksandr N . Ki y ko, Igor A. Kovalev
{"title":"使用 IBA CYCLONE 18/9 HC 回旋加速器生产以 18F 为基础的放射性药物时 β 放射性核素的积累分析","authors":"С. Д. Бринкевич, Д. И. Бринкевич, А. И. Киевицкая, А. Н. Кийко, И. А. Ковалёв, Sviatoslav D . Brinkevich, D. Brinkevich, H. I. Kiyavitskaya, Aliaksandr N . Ki y ko, Igor A. Kovalev","doi":"10.29235/1561-8358-2024-69-2-166-176","DOIUrl":null,"url":null,"abstract":"In order to clarify the scheme of radioactive waste management, the accumulation of undesirable beta-emitting radionuclides (PH) in the production of radiopharmaceuticals based on 18F using the IBA CYCLONE 18/9 HC cyclotron was investigated. It is shown that the dominant impurity PH is tritium, which is formed by the reaction of 18O(p, t) 16O when water is irradiated with [18O]H2O protons. The main proportion of 3H (about 95%) remains in the regenerated water. 1.6 % of the accumulated tritium activity is carried away from the synthesis zone with gases and water vapor. Tritium-containing waste (regenerated water in vials) can be considered as waste of a very low level of activity during disposal. With an increase in the operating time of the target over 2500 µA · h, the processes of corrosion /erosion of target materials increase, which leads to a sharp increase in the concentration of undesirable radionuclides in regenerated water, sorption purification cartridges and the finished dosage form. The concentration of tritium does not increase significantly. In the β-spectra of regenerated water [18O]H2O and the finished radiopharmaceutical [18F]NaF, in addition to the maximum due to tritium, a number of maxima appear in both the low- and high-energy parts of the spectrum. Other undesirable β-emitters accumulate in water as a result of leaching of the activated target wall. The possibility of using measurements of tritium activity in water [18O]H2O as an indicator of its re-enrichment has been demonstrated. The necessity of controlling the content of impurity beta-emitting PH in intermediate products, production waste and final radiopharmaceutical is shown.","PeriodicalId":516810,"journal":{"name":"Proceedings of the National Academy of Sciences of Belarus. Physical-technical series","volume":"90 10","pages":""},"PeriodicalIF":0.0000,"publicationDate":"2024-07-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Analysis of the accumulation of β-emitting radionuclides in the production of radiopharmaceuticals based on 18F using the IBA CYCLONE 18/9 HC cyclotron\",\"authors\":\"С. Д. Бринкевич, Д. И. Бринкевич, А. И. Киевицкая, А. Н. Кийко, И. А. Ковалёв, Sviatoslav D . Brinkevich, D. Brinkevich, H. I. Kiyavitskaya, Aliaksandr N . Ki y ko, Igor A. Kovalev\",\"doi\":\"10.29235/1561-8358-2024-69-2-166-176\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"In order to clarify the scheme of radioactive waste management, the accumulation of undesirable beta-emitting radionuclides (PH) in the production of radiopharmaceuticals based on 18F using the IBA CYCLONE 18/9 HC cyclotron was investigated. It is shown that the dominant impurity PH is tritium, which is formed by the reaction of 18O(p, t) 16O when water is irradiated with [18O]H2O protons. The main proportion of 3H (about 95%) remains in the regenerated water. 1.6 % of the accumulated tritium activity is carried away from the synthesis zone with gases and water vapor. Tritium-containing waste (regenerated water in vials) can be considered as waste of a very low level of activity during disposal. With an increase in the operating time of the target over 2500 µA · h, the processes of corrosion /erosion of target materials increase, which leads to a sharp increase in the concentration of undesirable radionuclides in regenerated water, sorption purification cartridges and the finished dosage form. The concentration of tritium does not increase significantly. In the β-spectra of regenerated water [18O]H2O and the finished radiopharmaceutical [18F]NaF, in addition to the maximum due to tritium, a number of maxima appear in both the low- and high-energy parts of the spectrum. Other undesirable β-emitters accumulate in water as a result of leaching of the activated target wall. The possibility of using measurements of tritium activity in water [18O]H2O as an indicator of its re-enrichment has been demonstrated. The necessity of controlling the content of impurity beta-emitting PH in intermediate products, production waste and final radiopharmaceutical is shown.\",\"PeriodicalId\":516810,\"journal\":{\"name\":\"Proceedings of the National Academy of Sciences of Belarus. Physical-technical series\",\"volume\":\"90 10\",\"pages\":\"\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2024-07-09\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Proceedings of the National Academy of Sciences of Belarus. 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Analysis of the accumulation of β-emitting radionuclides in the production of radiopharmaceuticals based on 18F using the IBA CYCLONE 18/9 HC cyclotron
In order to clarify the scheme of radioactive waste management, the accumulation of undesirable beta-emitting radionuclides (PH) in the production of radiopharmaceuticals based on 18F using the IBA CYCLONE 18/9 HC cyclotron was investigated. It is shown that the dominant impurity PH is tritium, which is formed by the reaction of 18O(p, t) 16O when water is irradiated with [18O]H2O protons. The main proportion of 3H (about 95%) remains in the regenerated water. 1.6 % of the accumulated tritium activity is carried away from the synthesis zone with gases and water vapor. Tritium-containing waste (regenerated water in vials) can be considered as waste of a very low level of activity during disposal. With an increase in the operating time of the target over 2500 µA · h, the processes of corrosion /erosion of target materials increase, which leads to a sharp increase in the concentration of undesirable radionuclides in regenerated water, sorption purification cartridges and the finished dosage form. The concentration of tritium does not increase significantly. In the β-spectra of regenerated water [18O]H2O and the finished radiopharmaceutical [18F]NaF, in addition to the maximum due to tritium, a number of maxima appear in both the low- and high-energy parts of the spectrum. Other undesirable β-emitters accumulate in water as a result of leaching of the activated target wall. The possibility of using measurements of tritium activity in water [18O]H2O as an indicator of its re-enrichment has been demonstrated. The necessity of controlling the content of impurity beta-emitting PH in intermediate products, production waste and final radiopharmaceutical is shown.