Radiation Dose to Medical Staff in 177Lu-PSMA-DKFZ-617 therapy And Estimation of Annual Dose

The results covered in this paper relate to the “Khoiniki” research sub-unit of a larger-scale sequence of studies focused on the local assessments of the present-day 241Am and 137Cs concentrations in the soils and locally produced foods, with the estimation of the public internal radiation doses in the residential areas of the Gomel region of the Republic of Belarus most closely adjacent to the ChNPP resettlement zone. The objective was to make a conservative estimate of a committed annual dose of internal exposure from 241Am and 137Сs received by the villagers of 96 farmsteads in 30 settlements of the private sector of Khoiniki countryside through both, inhalation and consumption of local foodstuffs. The results obtained in this study include an update of the existing contamination levels of 241Am and 137Сs present in the local soils and foods grown or produced in private backyards and households. 241Am in food samples was determined by alpha-spectroscopy radiochemical analysis with the use of selective extraction-chromatographic resins. Gamma-spectrometry techniques were used to measure 241Am in soil samples and 137Сs in soil and food samples. Based on our findings, the present-day deposition density of 241Am in the soils does not exceed 4 kBq/m2 , while the values of 137Cs contamination are by one to two orders of magnitude higher than that of 241Am and vary between 30 and 500 kBq/m2 . Generally, the values of activity concentration of 241Am detected in local soils are well within 10 Bq/kg in the majority of inspected villages, with the exception of three sites where higher levels of 241Am contamination is soils were detected ranging from 14 to 16 Bq/kg. The ambient dose rates in the countryside range from 0.05 to 0.38 μSv/hour, with the average of 0.15 μSv/hour. No cases of 137Сs contamination above the established reference levels of 80, 100 and 90 Bq/ kg have been found in the local food samples of, respectively, potatoes, vegetables (incl. roots and tubers) and grains. The content of 241Am in the staple foods produced in the area varies from single digits to tenths of mBq/ kg, which is less by three orders of magnitude than 137Сs activities concentrationd found in the same staples. Of the two pathways contributing to the local committed internal exposure from 241Am, the dominant one is through inhalation (0.006–0.038 mSv/year) prevailing over the consumption pathway of this same radioisotope by at least one order of magnitude. At the time of gardening and other household field works, the existing levels of 241Am contamination in soils are estimated to produce from 85 to 98% of the internal radiation dose received by individuals from inhaling the total of 241Am and 137Сs. The maximum committed annual doses of internal exposure from 137Сs are estimated to be above 1 mSv/year in 6 out of 30 villages engaged in our study. At the same time, the estimated internal radiation dose due to 241Am does not surpass 0.04 mSv/year. The 137Сs major contribution to the internal exposure of villages in the Khoiniki countryside is through food consumption.

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GAMOS DICOM Simulation on Occupational EL Dose due to 99mTc and 131I Exposures in Nuclear Medicine Departments

Journal of King Abdulaziz University-Engineering Sciences ◽

10.4197/eng.30-1.5 ◽

2019 ◽

Vol 30 (1) ◽

pp. 65-78

Author(s):

Abdulmalek Rajkhan Abdulmalek Rajkhan

Keyword(s):

Nuclear Medicine ◽

Radiation Dose ◽

Atomic Bomb ◽

Epidemiological Studies ◽

Radioactive Material ◽

Radiation Hazard ◽

Dose Limit ◽

Dicom Image ◽

Annual Dose ◽

Atomic Bomb Survivors

Radiation induced cataracts is a disease that is common amongst radiation exposed staff. About 30 percent of retired occupational radiation workers developed eye lens (EL) cataracts. Epidemiological studies on radiation therapy patients, occupational workers, and atomic bomb survivors show that 0.5 Gy of acute or fractioned radiation dose to EL causes one or both lens to cloud. The annual EL dose limit drawn by the International Commission for Radiation Protection (ICRP) was 150 mSv and was changed in 2012 to 20 mSv averaged over 5 years, with no single year exceeding 50 mSv. The limited number of researche done in Nuclear Medicine (NM) clinics with the Hp(3) dosimeters suggest that the annual EL dose from three procedures is measured to be between 4.5 and 9 mSv (i.e. dispensing, preparing and administering). These procedures are performed when the radioactive materials are in closed shielded containers or behind a barrier. Common radioactive material handled by occupational workers in NM clinics are 99mTc and 131I. They pose less radiation hazard to workers EL in the three procedures when they are behind shielded containers. Moreover, once the radioactive material is administered into patients, they become open sources and pose more radiation hazard to workers. The Hp(3) dosimeter is a new uncommon dosimeter. Many radiation facilities use the Hp(0.07) and Hp(10) dosimeters coupled with many conditions and conversion factors to find approximate results. Therefore, simulations are performed to find the EL dose. However, some simulations are performed with little flexibility in simulation geometry, others utilize low-quality phantoms or present the simulation results in terms of fluxes or energy ranges. In the present study, the NM worker EL dose is simulated by utilizing a high-resolution Digital Imagning Communication in Medicine (DICOM) image in GEANT4 Archeticture for Medical Oriented Simulation (GAMOS). A water cylinder homogenously filled by radioactive material, representing the administered patient, was created in the simulation. The worker exposure scenario was simulated by placing the cylinder in three different directions and five different distances with respect to the DICOM image. The results of the simulation reveal that the highest occupational EL radiation dose is received from the anterior-posterior direction, followed by the lateral, and the posterior-anterior directions. The results of the conservative simulated scenario reveal that the worker EL dose is exposed to three tenths of the annual dose limit after 110 131I patients, or 300 99mTc patients.

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Radiation dose to the lens of the eye in medical staff performing fluoroscopy

Deutsches Aerzteblatt Online ◽

10.3238/arztebl.m2021.0308 ◽

2021 ◽

Author(s):

Christiane Behr-Meenen ◽

Heiner von Boetticher ◽

Olena Lynnyk ◽

Christoph Langer ◽

Jan Felix Kersten ◽

...

Keyword(s):

Radiation Dose ◽

Medical Staff

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Evaluation of Ionizing Radiation in Five Private Radiology Centers in Khuzestan

Archives of Occupational Health ◽

10.18502/aoh.v4i1.2254 ◽

2020 ◽

Author(s):

Behzad Fouladi Dehaghi ◽

Jamileh Deris ◽

Maryam Mosavi Qahfarokhi ◽

Ameneh Golbaghi ◽

Leila Nematpour

Keyword(s):

Radiation Dose ◽

Ionizing Radiation ◽

Gamma Spectroscopy ◽

Surface Radiation ◽

Annual Dose ◽

Waiting Room ◽

X Ray ◽

Medicine Research ◽

Ionization Radiation ◽

Diagnostic Radiography

Background: Nowadays ionizing radiation is widely used in medicine, research and industry. In medicine, ionizing radiation is used to diagnose diseases and in high doses to treat diseases such as cancer. Undoubtedly, most exposure to artificial sources is in the field of medical and diagnostic radiology. Therefore, practitioners in the field of diagnostic radiography and patients are exposed to ionizing radiation and its risks. On the other hand, despite the advantages and efficacy of diagnostic radiation in the medical field, overall less attention is paid to optimizing and controlling protection in medical radiation. Therefore, the aim of this study was to evaluate the background ionizing radiation in Ahwaz diagnostic radiography centers. Methods: Ionization radiation levels were measured in and out of each center using gamma spectroscopy (Radiation Alert Inspector-EXP 15109) at a, b, c, d and e radiographic centers within one meter above the Earth's surface. Radiation levels within each center were measured at four locations (outside of center, secretary desk, and patient waiting room and behind the radiology room) both in X-ray machine operating and non-operating condition. The obtained data were analyzed by SPSS software. Results: The inside ionization radiation dose in a, b, c, d and e radiographic centers were 0.121, 0.119, 0.126, 0132 and 0.128 μSv/h respectively. The outside ionization radiation dose in a, b, c, d and e radiographic centers were 0.094, 0.092, 0.093, 0.112 and 0.101 μSv/h respectively. Equivalent annual dose within and outside selected radiology centers were lower than the threshold (1 mSv / year). Conclusion: The results show that the ionizing radiation dose of the X-ray equipment examined in the radiology centers of Ahwaz is lower than the global standard.

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Radiation Exposure to the Hand of a Spinal Interventionalist during Fluoroscopically Guided Procedures

Asian Spine Journal ◽

10.4184/asj.2017.11.1.75 ◽

2017 ◽

Vol 11 (1) ◽

pp. 75-81 ◽

Cited By ~ 4

Author(s):

Kazuta Yamashita ◽

Hisanori Ikuma ◽

Takuya Tokashiki ◽

Takashi Maehara ◽

Akihiro Nagamachi ◽

...

Keyword(s):

Radiation Dose ◽

Prospective Study ◽

Radiation Exposure ◽

Radiological Protection ◽

Dominant Hand ◽

Annual Dose ◽

Lead Apron ◽

Left Chest ◽

Glass Dosimeter ◽

The Right

<sec><title>Study Design</title>Prospective study.</sec><sec><title>Purpose</title>During fluoroscopically guided spinal procedure, the hands of spinal surgeons are placed close to the field of radiation and may be exposed to ionizing radiation. This study directly measured the radiation exposure to the hand of a spinal interventionalist during fluoroscopically guided procedures.</sec><sec><title>Overview of Literature</title>Fluoroscopically guided spinal procedures have been reported to be a cause for concern due to the radiation exposure to which their operators are exposed.</sec><sec><title>Methods</title>This prospective study evaluated the radiation exposure of the hand of one spinal interventionalist during 52 consecutive fluoroscopic spinal procedures over a 3-month period. The interventionalist wore three real-time dosimeters secured to the right forearm, under the lead apron over the chest, and outside the lead apron over the chest. Additionally, one radiophotoluminescence glass dosimeter was placed under the lead apron over the left chest and one ring radiophotoluminescence glass dosimeter was worn on the right thumb. The duration of exposure and radiation dose were measured for each procedure.</sec><sec><title>Results</title>The average radiation exposure dose per procedure was 14.9 µSv, 125.6 µSv, and 200.1 µSv, inside the lead apron over the chest, outside the lead apron over the chest, and on the right forearm, respectively. Over the 3-month period, the protected radiophotoluminescence glass dosimeter over the left chest recorded less than the minimum reportable dose, whereas the radiophotoluminescence glass ring dosimeter recorded 368 mSv for the thumb.</sec><sec><title>Conclusions</title>Our findings indicated that the cumulative radiation dose measured at the dominant hand may exceed the annual dose limit specified by the International Commission on Radiological Protection. Spinal interventionalists should take special care to limit the duration of fluoroscopy and radiation exposure.</sec>

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Occupational Radiation Dose, Especially for Eye Lens: Hp(3), in Medical Staff Members Involved in Computed Tomography Examinations

Applied Sciences ◽

10.3390/app11104448 ◽

2021 ◽

Vol 11 (10) ◽

pp. 4448

Author(s):

Minoru Osanai ◽

Hidenori Sato ◽

Kana Sato ◽

Kohsei Kudo ◽

Masahiro Hosoda ◽

...

Keyword(s):

Computed Tomography ◽

Radiation Dose ◽

Radiation Protection ◽

Medical Staff ◽

Shielding Effect ◽

Eye Lens ◽

Radiological Protection ◽

Ct Examination ◽

Radiation Dose Exposure ◽

Occupational Radiation

Radiation dose management of medical staff has become increasingly important. Particularly, based on the statement by the International Commission on Radiological Protection (ICRP) in 2011, a new lower equivalent dose limit for the eye lens is being established in each country. Although many reports have discussed the occupational radiation dose in interventional radiology (IR), few studies have examined the dose during computed tomography (CT) examinations. This study investigated the radiation dose exposure to medical staff present in the CT room during irradiation, with particular focus on the exposure to eye lens. The radiation dose exposure to those who assist patients during head, chest and upper abdomen CT examination was measured in a phantom study. The radiation dose exposure with scattered radiation was never negligible (i.e., high); Hp(3) was the highest in head CT examination, at 0.44 mSv per examination. Furthermore, the shielding effect of radiation protection glasses was large, and radiation protection glasses are useful tools for the medical staff who are involved in CT examinations. The justification and optimisation should be carefully considered in assistant actions.

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Hand monitoring in nuclear medicine departments in Croatia - first results

Nuclear Technology and Radiation Protection ◽

10.2298/ntrp2001082s ◽

2020 ◽

Vol 35 (1) ◽

pp. 82-86

Author(s):

Marija Suric-Mihic ◽

Robert Bernat ◽

Jerko Sisko ◽

Maja Vojnic-Kortmis ◽

Luka Pavelic ◽

...

Keyword(s):

Nuclear Medicine ◽

Radiation Protection ◽

Medical Staff ◽

Monitoring Programme ◽

Dose Limit ◽

Annual Dose ◽

First Results ◽

Personal Dosimetry ◽

Radioactive Sources ◽

One Year

Individual hand monitoring for workers who manipulate unsealed radioactive sources in nuclear medicine is a necessity and the results can serve as the base for optimization processes. We performed an analysis of individual hand doses for medical staff preparing and applying radiopharmaceuticals (99mTc, 123I, 201Tl, 131I, or 125I) in three Croatian clinical hospitals, for a period of one year since extremity monitoring became legally mandatory in Croatia. The majority of annual hand doses for workers were below or slightly above 150 mSv per year with only a few workers exceeding the annual dose limit of 500 mSv. The analysis confirmed that the radiation protection expert's role in an individual monitoring programme and personal dosimetry is crucial in order to achieve the optimal radiation protection of workers.

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