Some aspects of radiation protection in radionuclide therapy departments
The paper presents the data that allow calculate the attenuation factors in lead, tungsten and concrete of various thicknesses or the thickness of shielding made of these materials for a given attenuation factor for the spectra of gamma radiation of 131I and 177Lu radionuclides. Using these data the...
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Saint-Petersburg Research Institute of Radiation Hygiene after Professor P.V. Ramzaev
2021-04-01
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doaj-3b5b717e8d1f4e828d3dc75b155d05512021-07-29T08:21:52ZengSaint-Petersburg Research Institute of Radiation Hygiene after Professor P.V. RamzaevRadiacionnaâ Gigiena1998-426X2021-04-01141758510.21514/1998-426X-2021-14-1-75-85690Some aspects of radiation protection in radionuclide therapy departmentsV. Yu. Golikov0L. A. Chipiga1A. V. Vodovatov2M. Ya. Smolyarchuk3Saint-Petersburg Research Institute of Radiation Hygiene after Professor P.V. Ramzaev, Federal Service for Surveillance on Consumer Rights Protection and Human Well-BeingSaint-Petersburg Research Institute of Radiation Hygiene after Professor P.V. Ramzaev, Federal Service for Surveillance on Consumer Rights Protection and Human Well-Being; A.M. Granov Russian Scientific Center of Radiology and Surgical TechnologiesSaint-Petersburg Research Institute of Radiation Hygiene after Professor P.V. Ramzaev, Federal Service for Surveillance on Consumer Rights Protection and Human Well-Being; Saint Petersburg State Pediatric Medical UniversityScientific and Practical Clinical Center for Diagnostics and Telemedicine Technologies of the Moscow Department of HealthThe paper presents the data that allow calculate the attenuation factors in lead, tungsten and concrete of various thicknesses or the thickness of shielding made of these materials for a given attenuation factor for the spectra of gamma radiation of 131I and 177Lu radionuclides. Using these data the effectiveness of the protection of supporting equipment (portable containers, shielded syringes, etc.) and the possible doses of external radiation of medical personnel in the radionuclide therapy department were calculated. It is shown that there are short-term operations in the production process when a radiation source (container with a capsule with activity, syringe with activity), being near the body of a medical worker, creates a significant dose rate. For this reason the annual individual dose of external exposure of a medical worker can approach or exceed 1/3 of the dose limit. Calculation of the attenuation of 131I gamma radiation by stationary shield showed that the thickness of walls and floors made of concrete 200 – 400 mm will ensure that the permissible values of the dose rates of gamma radiation in the air do not exceed at annual turnover of activity in the radionuclide therapy department of ~ 3.3 · 1012 Bq.https://www.radhyg.ru/jour/article/view/772radionuclide therapyiodine-131medical personnelprotection from gamma radiation |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
V. Yu. Golikov L. A. Chipiga A. V. Vodovatov M. Ya. Smolyarchuk |
spellingShingle |
V. Yu. Golikov L. A. Chipiga A. V. Vodovatov M. Ya. Smolyarchuk Some aspects of radiation protection in radionuclide therapy departments Radiacionnaâ Gigiena radionuclide therapy iodine-131 medical personnel protection from gamma radiation |
author_facet |
V. Yu. Golikov L. A. Chipiga A. V. Vodovatov M. Ya. Smolyarchuk |
author_sort |
V. Yu. Golikov |
title |
Some aspects of radiation protection in radionuclide therapy departments |
title_short |
Some aspects of radiation protection in radionuclide therapy departments |
title_full |
Some aspects of radiation protection in radionuclide therapy departments |
title_fullStr |
Some aspects of radiation protection in radionuclide therapy departments |
title_full_unstemmed |
Some aspects of radiation protection in radionuclide therapy departments |
title_sort |
some aspects of radiation protection in radionuclide therapy departments |
publisher |
Saint-Petersburg Research Institute of Radiation Hygiene after Professor P.V. Ramzaev |
series |
Radiacionnaâ Gigiena |
issn |
1998-426X |
publishDate |
2021-04-01 |
description |
The paper presents the data that allow calculate the attenuation factors in lead, tungsten and concrete of various thicknesses or the thickness of shielding made of these materials for a given attenuation factor for the spectra of gamma radiation of 131I and 177Lu radionuclides. Using these data the effectiveness of the protection of supporting equipment (portable containers, shielded syringes, etc.) and the possible doses of external radiation of medical personnel in the radionuclide therapy department were calculated. It is shown that there are short-term operations in the production process when a radiation source (container with a capsule with activity, syringe with activity), being near the body of a medical worker, creates a significant dose rate. For this reason the annual individual dose of external exposure of a medical worker can approach or exceed 1/3 of the dose limit. Calculation of the attenuation of 131I gamma radiation by stationary shield showed that the thickness of walls and floors made of concrete 200 – 400 mm will ensure that the permissible values of the dose rates of gamma radiation in the air do not exceed at annual turnover of activity in the radionuclide therapy department of ~ 3.3 · 1012 Bq. |
topic |
radionuclide therapy iodine-131 medical personnel protection from gamma radiation |
url |
https://www.radhyg.ru/jour/article/view/772 |
work_keys_str_mv |
AT vyugolikov someaspectsofradiationprotectioninradionuclidetherapydepartments AT lachipiga someaspectsofradiationprotectioninradionuclidetherapydepartments AT avvodovatov someaspectsofradiationprotectioninradionuclidetherapydepartments AT myasmolyarchuk someaspectsofradiationprotectioninradionuclidetherapydepartments |
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