Assessments of DNA Damage and Radiation Exposure Dose in Cattle Living in the Contaminated Area Caused by the Fukushima Nuclear Accident

Cathlab radiation workers, when performing interventional procedures, are at high risk of the effects of radiation exposure. The risk of radiation exposure is deterministic and stochastic biological effects. Therefore, radiation exposure studies of radiation workers at the cath lab were conducted to determine the value of radiation exposure received. This radiation exposure study was conducted by measuring and recording radiation exposure doses received by radiation workers. Measurements are made when the radiation officer performs the intervention procedure. The research was carried out for one month in the cath lab room of the Adam Malik General Hospital, Medan. The modalities used are GE Medical System Interventional Fluoroscopy and Phillips Allura Xper FD20. The dosimeter used is “my dose mini”, which is placed inside a shield or apron worn by radiation workers. The size of the apron shield used is 0.50 mm Pb at the front and 0.25 mm Pb at the rear. Radiation officers whose radiation exposure dose was measured consisted of 10 doctors, 11 nurses, and one radiographer. Each inspection procedure of each radiation worker has a different distance, time, and shield from the radiation source. The measurement of radiation exposure dose is (1-59 μSv) for doctors, (1-58 μSv) for nurses, and 1 μSv for radiographers. To protect against radiation must pay attention to the factors of time, distance, and shielding. Ways that can do are to avoid being close to radiation sources for too long, keep a space at a safe level from radiation, and use shields such as Pb-coated aprons, use Pb gloves, Pb goggles, and thyroid protectors. The amount of radiation exposure dose received by each radiation worker at the time of measurement is still within the tolerance limit. The Nuclear Energy Regulatory Agency (BAPETEN) regulation, which the International Commission recommends on Radiological Protection (ICRP), is 20 mSv/year. The results of this study are expected to be used as input for improving the quality of service for monitoring radiation exposure doses in the Cathlab and as reference material for further research.

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Correction: Association between ultraviolet radiation exposure dose and cataract in Han people living in China and Taiwan: A cross-sectional study

PLoS ONE ◽

10.1371/journal.pone.0222679 ◽

2019 ◽

Vol 14 (9) ◽

pp. e0222679

Author(s):

Keyword(s):

Ultraviolet Radiation ◽

Radiation Exposure ◽

Cross Sectional Study ◽

Exposure Dose ◽

Sectional Study ◽

Cross Sectional ◽

Ultraviolet Radiation Exposure ◽

Radiation Exposure Dose

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Introductory Chapter: Radiation Exposure, Dose and Protection

Ionizing and Non-ionizing Radiation ◽

10.5772/intechopen.89041 ◽

2020 ◽

Author(s):

Otolorin Adelaja Osibote

Keyword(s):

Radiation Exposure ◽

Exposure Dose ◽

Radiation Exposure Dose

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Long-term assessment of airborne radiocesium after the Fukushima nuclear accident: Re-suspension from bare soil and forest ecosystems

10.5194/acp-2016-270 ◽

2016 ◽

Author(s):

M. Kajino ◽

M. Ishizuka ◽

Y. Igarashi ◽

K. Kita ◽

C. Yoshikawa ◽

...

Keyword(s):

Land Surface ◽

Forest Ecosystems ◽

Field Experiments ◽

Dust Emission ◽

Nuclear Accident ◽

Fukushima Nuclear Accident ◽

Emission Model ◽

Air Concentration ◽

Contaminated Area

Abstract. The long-term effect of 137Cs re-suspension from contaminated soil and forests due to the Fukushima nuclear accident has been quantitatively assessed by numerical simulation, a field experiment on dust emission flux in the contaminated area (Namie, Fukushima), and air concentration measurements inside (Namie) and outside (Tsukuba, Ibaraki) the contaminated area. The assessment period is for the year 2013 just after the start of the field experiments, December 14, 2012. The 137Cs concentrations at Namie and Tsukuba were approximately 10−1–1 and 10−2–10−1 mBq/m3, respectively. The observed monthly median concentration at Namie was one to two orders of magnitude larger than that at Tsukuba. This observed difference between the two sites was consistent with the simulated difference, indicating successful modeling of 137Cs re-suspension and atmospheric transport. The estimated re-suspension rate was approximately 10−6/d, which was significantly lower than the decreasing rate of the ambient gamma dose rate in Fukushima prefecture (10−4–10−3/d) as a result of radioactive decay, land surface processes (migration in the soil and biota), and decontamination. Consequently, re-suspension contributed negligibly to reducing ground radioactivity. The dust emission model could account for the air concentration of 137Cs in winter, whereas the summer air concentration was underestimated by one to two orders of magnitude. Re-suspension from forests at a constant rate of 10−7/h, multiplied by the green area fraction, quantitatively accounted for the air concentration of 137Cs at Namie and its seasonal variation. The simulated contribution of dust re-suspension to the air concentration was 0.6–0.8 in the cold season and 0.1–0.4 in the warm season at both sites; the remainder of the contribution was re-suspension from forest. The re-suspension mechanisms, especially through the forest ecosystems, remain unknown, and thus the current study is the first but crude estimation of the long-term assessment of radiocesium re-suspension. Further study will be needed to understand the re-suspension mechanisms and to accurately assess the re-suspension mechanisms through field experiments and numerical simulations.

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