vestiftИзвестия Национальной академии наук Беларуси. Серия физико-технических наукProceedings of the National Academy of Sciences of Belarus. Physical-technical series1561-83582524-244XThe Republican Unitary Enterprise Publishing House "Belaruskaya Navuka"10.29235/1561-8358-2024-69-2-166-176vestift-841Research ArticleДИАГНОСТИКА И БЕЗОПАСНОСТЬ ТЕХНИЧЕСКИХ И ПРИРОДНЫХ СИСТЕМDIAGNOSTICS AND SAFETY OF TECHNICAL AND ENVIRONMENT SYSTEMSАнализ накопления β-излучающих радионуклидов в процессе производства радиофармпрепаратов на основе 18F с использованием циклотрона IBA CYCLONE 18/9 HCAnalysis of the accumulation of β-emitting radionuclides in the production of radiopharmaceuticals based on 18F using the IBA CYCLONE 18/9 HC cyclotronhttps://orcid.org/0000-0003-1661-5272БринкевичС. Д.BrinkevichS. D.

Бринкевич Святослав Дмитриевич – кандидат химических наук, доцент кафедры радиационной химии и химической технологии

пр. Независимости, 4, 220030, Минск, Республика Беларусь;

руководитель направления радиохимии

Октябрьский пр., 122, 188640, Всеволожск, Ленинградская область, Российская Федерация

Sviatoslav D. Brinkevich – Cand. Sci. (Chemistry), Associate Professor of the Department of Radiation Chemistry and Chemical Technology

4, Nezavisimosti Ave., 220030, Minsk;

Head of the Radiochemistry Department

122, Oktyabrski Ave., 188640, Vsevolozhsk, Leningrad Region, Russian Federation

brinkevichSD@bsu.byБринкевичД. И.BrinkevichD. I.

Бринкевич Дмитрий Иванович – кандидат физико-математических наук, ведущий научный сотрудник кафедры физики полупроводников и наноэлектроники

пр. Независимости, 4, 220030, Минск, Республика Беларусь

Dmitrii I. Brinkevich – Cand. Sci. (Physics and Mathematics), Leading Researcher at the Department of Semiconductor Physics and Nanoelectronics

4, Nezavisimosti Ave., 220030, Minsk

brinkevich@bsu.byhttps://orcid.org/0000-0001-9816-334XКиевицкаяА. И.KiyavitskayaH. I.

Киевицкая Анна Ивановна – доктор физико-математических наук, кандидат технических наук, доцент, профессор кафедры ядерной и радиационной безопасности

ул. Долгобродская 23/1, 220070, Минск

Hanna I. Kiyavitskaya – Dr. Sci. (Physics and Mathematics), Cand. Sci. (Engineering), Associate Professor, Professor of the Department of Nuclear and Radiation Safety

23/1, Dolgobrodskaya Str., 220037, Minsk

kiyavitskaya@iseu.byКийкоА. Н.KiykoA. N.

Кийко Александр Николаевич – начальник отдела измерений ионизирующих излучений

Старовиленский тракт, 93, 220053, Минск

Aliaksandr N. Kiyko – Head of the Ionizing Radiation Measurement Department

93, Starovilenski tract, 220053, Minsk

kiyko@micasensor.comКовалевИ. А.KovalevI. A.

Ковалев Игорь Александрович – заведующий изотопной циклотронно-радиохимической лабораторией

а/г Лесной, 223040, Минский район

Igor A. Kovalev – Head of the Isotope Cyclotron Radiochemical Laboratory

agro-town Lesnoy, 223040, Minsk District

igor.alex.kovalev@gmail.comБелорусский государственный университет; ООО «Мой медицинский центр – высокие технологии»Belarusian State University; LLC “My Medical Center – High Technologies”Белорусский государственный университетBelarusian State UniversityМеждународный государственный институт имени А. Д. Сахарова Белорусского государственного университетаInternational Sakharov Environmental Institute Belarusian State UniversityБелорусский государственный институт метрологииBelarusian State Institute of MetrologyРеспубликанский научно-практический центр онкологии и медицинской радиологии имени Н. Н. АлександроваN. N. Alexandrov National Cancer Centre of Belarus202409072024692166176Copyright © Бринкевич С.Д., Бринкевич Д.И., Киевицкая А.И., Кийко А.Н., Ковалев И.А., 20242024Бринкевич С.Д., Бринкевич Д.И., Киевицкая А.И., Кийко А.Н., Ковалев И.А.Brinkevich S.D., Brinkevich D.I., Kiyavitskaya H.I., Kiyko A.N., Kovalev I.A.Данная работа распространяется под лицензией Creative Commons Attribution 4.0.This work is licensed under a Creative Commons Attribution 4.0 License.https://vestift.belnauka.by/jour/article/view/841

С целью уточнения схемы обращения с радиоактивными отходами исследовано накопление нежелательных β-излучающих радионуклидов (РН) при производстве радиофармпрепаратов на основе 18F с использованием циклотрона IBA CYCLONE 18/9 HC. Показано, что доминирующим примесным РН является тритий, образующийся по реакции 18О(р, t) 16О при облучении воды [18O]H2O протонами. Основная доля 3Н (около 95 %) остается в регенерированной воде; 1,6 % от наработанной активности трития уносится из зоны синтеза с газами и парами воды. Содержащие тритий отходы (регенерированная вода во флаконах) при утилизации могут рассматриваться как отходы очень низкого уровня активности. При увеличении времени наработки мишени свыше 2500 мкА·ч усиливаются процессы коррозии/эрозии материалов мишени, что приводит к резкому росту концентрации нежелательных радионуклидов в регенерированной воде, картриджах сорбционной очистки и готовой лекарственной форме. Концентрация трития при этом существенно не возрастает. В β-спектрах регенерированной воды [ 18O]H2O и готового радиофармпрепарата [18F]NaF, кроме максимума, обусловленного тритием, появляется ряд максимумов как в низко-, так и в высокоэнергетической части спектра. Другие нежелательные β-излучатели накапливаются в воде в результате выщелачивания активированной стенки мишени. Продемонстрирована возможность использования измерений активности трития в воде [18O]H2O в качестве индикатора ее повторного обогащения. Показана необходимость контроля содержания примесных β-излучающих РН в промежуточных продуктах, отходах производства и конечном радиофармпрепарате.

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.

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The authors declare that there are no conflicts of interest present.