radhydРадиационная гигиенаRadiatsionnaya Gygiena = Radiation Hygiene1998-426X2409-9082NIIRG10.21514/1998-426X-2025-18-2-109-121radhyd-1157Research ArticleРАДИАЦИОННЫЕ ИЗМЕРЕНИЯRADIATION MEASUREMENTSИзмерение эффективной удельной активности природных радионуклидов in situ для оценки мощности амбиентного эквивалента дозы в городской средеMeasurement of effective activity concentration of natural radionuclides insitu for assessment of ambient dose equivalent rate in urban environmentsРамзаевВ. П.RamzaevV. P.

Рамзаев Валерий Павлович – кандидат медицинских наук, ведущий научный сотрудник лаборатории внешнего облучения 

197101, Санкт-Петербург, ул. Мира, д. 8 

Valery P. Ramzaev – Candidate of Medical Sciences, Leading Researcher of the Laboratory of External Exposure

V.Ramzaev@mail.ruБарковскийА. Н.BarkovskyA. N.

Барковский Анатолий Николаевич – руководитель Федерального радиологического центра, главный научный сотрудник

Санкт-Петербург

Anatoly N. Barkovsky – Head of the Federal Radiological Centre 

Санкт-Петербургский научно-исследовательский институт радиационной гигиены имени профессора П.В. Рамзаева, Федеральная служба по надзору в сфере защиты прав потребителей и благополучия человекаРоссияSaint Petersburg Research Institute of Radiation Hygiene after Professor P.V. Ramzaev, Federal Service for Surveillance of Consumer Rights Protection and Human WellbeingRussian Federation202514072025182109121Copyright © Рамзаев В.П., Барковский А.Н., 20252025Рамзаев В.П., Барковский А.Н.Ramzaev V.P., Barkovsky A.N.Данная работа распространяется под лицензией Creative Commons Attribution 4.0.This work is licensed under a Creative Commons Attribution 4.0 License.https://www.radhyg.ru/jour/article/view/1157

В настоящее время мощность дозы гамма-излучения в воздухе от техногенных радионуклидов на загрязненных в результате аварии на ЧАЭС территориях заметно снизилась и во многих случаях сравнима с мощностью дозы гамма-излучения от природных радионуклидов. Поэтому при проведении оценки доз техногенного облучения населения этих территорий очень важно корректно оценить вклад природного облучения. Применение полевой гамма-спектрометрии (измерения in situ) позволяет решать эту задачу непосредственно на месте без отбора проб окружающей среды и последующих лабораторных исследований. Для измерений in situ наиболее удобно использовать гаммаспектрометры, которые одновременно измеряют и мощность дозы, и эффективную удельную активность природных радионуклидов (226Ra, 232Th и 40K). Последняя величина однозначно связана с мощностью дозы гамма-излучения от природных радионуклидов при проведении измерений в геометрии 2π. Возможность применения результатов измерения эффективной удельной активности для отличных от 2π геометрий, в частности, в городской среде, требует обоснования. Целью данного исследования являлось эмпирическое определение соотношения между значениями мощности амбиентного эквивалента дозы от природных радионуклидов и результатами измерения эффективной удельной активности природных радионуклидов in situ в типичных городских локациях. Материалы и методы: Одновременные измерения (n = 170) общей мощности амбиентного эквивалента дозы и эффективной удельной активности были проведены в городе Санкт-Петербург (Россия) в весенне-осенний период в 2017–2024 гг. с использованием портативного гаммаспектрометра-дозиметра, расположенного в рюкзаке на спине у оператора. Результаты: По результатам измерений in situ был вычислен коэффициент перехода от эффективной удельной активности к мощности амбиентного эквивалента дозы ((нЗв/ч)/(Бк/кг)). Средняя величина ± стандартное отклонение коэффициента перехода для локации «улица», «двор», «площадь», «набережная», «мост», «парк-газон» и «парк-пешеходная дорожка» составила 0,55 ± 0,02 (n = 70), 0,55 ± 0,01 (11), 0,55 ± 0,02 (10), 0,54 ± 0,01 (9), 0,54 ± 0,04 (16), 0,57 ± 0,02 (27) и 0,54 ± 0,01 (27) соответственно. Заключение: Полученные значения коэффициента перехода могут быть использованы при проведении пешеходных обследований городов для определения вклада природных радионуклидов в суммарную мощность дозы гамма-излучения в случае радиоактивного загрязнения окружающей среды.

At present, the dose rate of gamma radiation from technogenic radionuclides in the territories contaminated as a result of the Chernobyl accident has significantly decreased and, in many cases, is comparable to the dose rate of gamma radiation from natural radionuclides. Therefore, when assessing the external doses to the population at these territories, it is important to correctly evaluate the contribution of natural radiation. The use of field gamma spectrometry (in situ measurements) allows solving this task directly on site without collection of environmental samples and subsequent analytical procedures in laboratory. For the in situ measurements, it is most convenient to use the gamma spectrometers that simultaneously measure both the dose rate in air and the effective activity concentration of natural radionuclides (226Ra, 232Th and 40K). The latter value is unambiguously related to the dose rate of gamma radiation from natural radionuclides when measurements are carried out in the 2π geometry. The possibility of using the results of measuring the effective activity concentration in conditions different from the 2π geometry, in particular, in an urban environment, requires justification. The aim of the study was to empirically determine the relationship between the ambient dose equivalent rate from natural radionuclides and the effective activity concentration of natural radionuclides in typical urban locations. Materials and methods. Simultaneous measurements (n = 170) of the total ambient dose equivalent rate and effective activity concentration were performed in the city of St. Petersburg (Russia) in the spring-autumn period in 2017–2024 using a portable gamma spectrometerdosimeter. The device was placed in a backpack on the operator's back. Main results. Based on results of the in situ measurements, the conversion coefficient from effective activity concentration to ambient dose equivalent rate ((nSv/h)/(Bq/kg)) was calculated. The mean ± standard deviation value of the conversion coefficient for the location “street”, “courtyard”, “square”, “embankment”, “bridge”, “park-lawn”, and “park-footpath” was 0.55 ± 0.02 (n = 70), 0.55 ± 0.01 (11), 0.55 ± 0.02 (10), 0.54 ± 0.01 (9), 0.54 ± 0.04 (16), 0.57 ± 0.02 (27), and 0.54 ± 0.01 (27), respectively. Conclusion. The obtained values of the conversion coefficient can be used when performing walk surveys of urban areas to determine contribution of natural sources to the total dose rate of gamma radiation in the case of radioactive contamination of the environment.

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