• Title/Summary/Keyword: Natural radiation dose rate

검색결과 39건 처리시간 0.025초

스키장의 자연방사선량 측정(경기도 지역을 중심으로) (Measurement of the Natural Radiation Dose in the Ski Field (Focusing on the Gyeonggi Province area))

  • 정홍문;정재은
    • 한국방사선학회논문지
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    • 제11권3호
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    • pp.117-122
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    • 2017
  • 레저생활의 급증으로 인하여 스키장 사용 인구가 급격히 증가하고 있다. 스키장은 직접적으로 자연광이나 우주선을 받을 확률이 높다. 왜냐하면 고도가 존재하는 산에 위치하기 때문이다. 일반적으로 고도가 높아질수록 자연방사선량이 증가한다는 사실은 널리 알려져 있다. 하지만 아직까지 스키장 고도에 관한 자연방사선량은 보고되지 않았다. 국내에는 다양한 스키장이 존재를 하지만 이번논문에서는 경기도 지역의 스키장4곳을 선정하여 고도에 따른 자연방사선량을 측정하였다. 결과적으로 스키장은 고도가 낮은 일반생활 지역에서보다는 방사선량보다 조금 많은 방사선량이 측정되었다. 우려할 수준은 아니지만 스키장 이용 시에는 반드시 스키 장비인 고글이나 다양한 스키 웨어(고글, 마스크, 헬멧)를 착용하여 자연방사선량을 보호한다면 환경방사선으로부터 안전하게 스키를 즐길 수 있을 것이다.

국내 수처리시설 종사자 작업유형에 따른 외부피폭방사선량 평가 (Assessment of External Radiation Dose for Workers in Domestic Water Treatment Facility According to the Working Type)

  • 전성훈;이성연;김혁재;김민성;김광표
    • 방사선산업학회지
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    • 제17권2호
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    • pp.151-160
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    • 2023
  • The International Atomic Energy Agency (IAEA) proposes 11 industries that handle Naturally Occurring Radioactive Material (NORM) that are considered to need management. A water treatment facility is one of the above industries that takes in groundwater and produces drinking water through a water treatment process. Groundwater can accumulate natural radionuclides such as uranium and thorium in raw water by contacting rocks or soil containing natural radionuclides. Therefore, there is a possibility that workers in water treatment facilities will be exposed due to the accumulation of natural radionuclides in the water treatment process. The goal of this study is to evaluate the external radiation dose according to the working type of workers in water treatment facilities. In order to achieve the above goal, the study was conducted by dividing it into 1) analysis of the exposure environment, 2) measurement of the external radiation dose rate 3) evaluation of the external radiation dose. In the stage of analyzing the exposure environment, major processes that are expected to occur significantly were derived. In the measurement stage of the external radiation dose rate, a map of the external radiation dose rate was prepared by measuring the spatial radiation dose rate in major processes. Through this, detailed measurement points were selected considering the movement of workers. In the external radiation dose evaluation stage, the external radiation dose was evaluated based on the previously derived external radiation dose rate and working time. As a result of measuring the external radiation dose rate at the detailed points of water treatment facilities A to C, it was 1.90×10-1 to 3.75×100 μSv h-1, and the external radiation dose was analyzed as 3.27×10-3 to 9.85×10-2 mSv y-1. The maximum external radiation dose appeared during the disinfection and cleaning of activated carbon at facility B, and it is judged that natural radionuclides were concentrated in activated carbon. It was found that the external radiation dose of workers in the water treatment facility was less than 1mSv y-1, which is about 10% of the dose limit for the public. As a result of this study, it was found that the radiological effect of external radiation dose of domestic water treatment facility workers was insignificant. The results are expected to contribute as background data to present optimized safety management measures for domestic NORM industries in the future.

우리나라 남동지방(南東地方)의 환경방사선(環境放射線) 선량율(線量率)의 결정(決定)(1980년도(年度)) (Determination of Environmental Radiation Dose Rate in the Southeastern Korea)

  • 노재식;이현덕
    • Journal of Radiation Protection and Research
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    • 제5권1호
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    • pp.1-6
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    • 1980
  • A portable count-ratemeter and a thermoluminescent detector ($CaSO_4:Dy$) have been used to obtain total gamma dose rates at approximately 50 locations during the course of several survey trips in the southeastern Korea. The purposes of these measurement were to provide a future reference data and to establish the approximate range of population exposure to the natural environmental radiation. The natural levels encountered ranged from a low of 14.6 microroentgen per hour to a high of 18.9 microroentgen per hour with a mean of $16.3{\pm}1.0$ microroentgen per hour. Among these results are the relatively high natural dose rate levels in the Masan area and Yangsan-Tongdosa area with the relatively low natural dose rate levels in the Gyeongsan-Cheongdo area and the Samrangjin-Jinyeong-Gimhae area.

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The role of natural rock filler in optimizing the radiation protection capacity of the intermediate-level radioactive waste containers

  • Tashlykov, O.L.;Alqahtani, M.S.;Mahmoud, K.A.
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3849-3854
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    • 2022
  • The present work aims to optimize the radiation protection efficiency for ion-selective containers used in the liquid treatment for the nuclear power plant (NPP) cooling cycle. Some naturally occurring rocks were examined as filler materials to reduce absorbed dose and equivalent dos received from the radioactive waste container. Thus, the absorbed dose and equivalent dose were simulated at a distance of 1 m from the surface of the radioactive waste container using the Monte Carlo simulation. Both absorbed dose and equivalent dose rate are reduced by raising the filler thickness. The total absorbed dose is reduced from 7.66E-20 to 1.03E-20 Gy, and the equivalent dose is rate reduced from 183.81 to 24.63 µSv/h, raising the filler thickness between 0 and 17 cm, respectively. Also, the filler type significantly affects the equivalent dose rate, where the redorded equivalent dose rates are 24.63, 24.08, 27.63, 33.80, and 36.08 µSv/h for natural rocks basalt-1, basalt-2, basalt-sill, limestone, and rhyolite, respectively. The mentioned results show that the natural rocks, especially a thicker thickness (i.e., 17 cm thickness) of natural rocks basalt-1 and basalt-2, significantly reduce the gamma emissions from the radioactive wastes inside the modified container. Moreover, using an outer cementation concrete wall of 15 cm causes an additional decrease in the equivalent dose rate received from the container where the equivalent dose rate dropped to 6.63 µSv/h.

콘크리트 공동주택과 근린생활 시설의 환경방사선에 관한 연구 (A Study on the Environmental Radiation of Concrete Apartments and Neighborhood Living Facilities)

  • 지태정;곽병준;민병인
    • 한국안전학회지
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    • 제24권2호
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    • pp.100-104
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    • 2009
  • In this study, the space gamma dose rates in the apartments structured with concrete were measured in accordance with construction year. In addition, the environmental radiation rates coming from the subway platforms and the road tunnels were analyzed in the equivalent dose by multiplying the absorbed dose with the radiation weighting factors. The space gamma dose rates measured in apartments were higher than those of outdoor which was $0.08{\sim}0.11uSv/h$ in the natural conditions. Especially, the older construction year is, the higher becomes space gamma dose rate. The average gamma dose rates in the subway platforms were measured. In the case of Busan and Daegu subway, the earlier the opening year is, the higher becomes dose rate. However, the dose rates of Seoul subway Lines were high overall, regardless of opening year. Seoul subway Line 6 showed the highest value of 0.21uSv/h. The gamma dose rate in road tunnels was higher than one of the outdoor and increased with opening year like as apartment. In dose rate comparison of the concrete structures with the outdoor, therefore, the space gamma dose rate of indoor is higher than one of the outdoor and the older structures have a higher dose rate.

Use of big data analysis to investigate the relationship between natural radiation dose rates and cancer incidences in Republic of Korea

  • Joo, Han Young;Kim, Jae Wook;Moon, Joo Hyun
    • Nuclear Engineering and Technology
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    • 제52권8호
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    • pp.1798-1806
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    • 2020
  • In this study, we investigated whether there is a significant relationship between the natural radiation dose rate and the cancer incidences in Korea by using a big data analysis. The natural dose rate data for this analysis were the measurement data obtained from the 171 monitoring posts of the 113 administrative districts in Korea over the 10 years from 2007 to 2016. The relative cancer incidences for this analysis were the difference in the cancer patients per hundred thousand people year-on-year in the administrative districts with the five highest and the five lowest natural gamma dose rates each year over the same period. To analyze the correlation between the two variables, Spearman's rank correlation coefficient between the two rates was derived using R, a well-known big data analysis tool. The analysis showed that Spearman's rank correlation coefficient was more than 0.05 and that the correlation between the two variables was not statistically significant.

Assessment of the terrestrial gamma radiation dose in Korea

  • Choi, Seok-Won;Yun, Ju-Yong;Kim, Chang-Kyu;Rho, Byung-Hwan;Lee, Jong-Seong
    • Journal of Radiation Protection and Research
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    • 제30권4호
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    • pp.161-165
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    • 2005
  • The gamma-ray dose rates in air at 233 locations in Korea have been determined. The contribution to the gamma-ray dose rates in air due to the presence of $^{232}Th-series,\;^{238}U-series\;and\;^{40}K$ is as follows: 47.3% $(36\;nGyh^{-1})\;^{232}Th-series$ 14.5% $(11\;nGyh^{-1})\;^{238}U-series$ and 38.2% $(29\;nGyh^{-1})\;^{40}K$. The mean gamma-ray dose rate theoretically derived from $^{232}Th-series,\;^{238}U-series\;and\;^{40}K\;was\;76{\pm}17\;nGyh^{-1}$. This corresponds to an annual effective dose of $410\;{\mu}Sv$ and an annual collective dose of 18900 person-Sv for all provinces under study. The results have been compared with other global radiation dose.

Distribution and characteristics of radioactivity$(^{232}Th,\;^{226}Ra,\;^{40}K,\;^{137}Cs\;and\;^{90}Sr)$ and radiation in Korea

  • Yun, Ju-Yong;Choi, Seok-Won;Kim, Chang-Kyu;Moon, Jong-Yi;Rho, Byung-Hwan
    • Journal of Radiation Protection and Research
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    • 제30권4호
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    • pp.167-174
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    • 2005
  • The concentrations of natural and artificial radionuclides in soil and gamma ray dose rate in air at 233 locations in Korea have been determined. The national mean concentrations of $^{232}Th,\;^{226}Ra,\;^{40}K,\;^{137}Cs\;and\;^{90}Sr$ in soil were $60{\pm}31,\;33{\pm}14,\;673{\pm}238,\;35{\pm}9.3\;and\;5.0{\pm}3.4\;Bq\;kg^{-1}$, respectively. The mean gamma-ray dose rate at 1 m above the ground was $7918\;nGy\;h^{-1}$. $^{137}Cs$ concentration had highly significant correlation with organic matter content and cation exchange capacity. $^{90}Sr$ concentration had slightly coherent with pH. The results have been compared with other global radioactivity and radiation measurements.

Dose Estimation Model for Terminal Buds in Radioactively Contaminated Fir Trees

  • Kawaguchi, Isao;Kido, Hiroko;Watanabe, Yoshito
    • Journal of Radiation Protection and Research
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    • 제47권3호
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    • pp.143-151
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    • 2022
  • Background: After the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident, biological alterations in the natural biota, including morphological changes of fir trees in forests surrounding the power plant, have been reported. Focusing on the terminal buds involved in the morphological formation of fir trees, this study developed a method for estimating the absorbed radiation dose rate using radionuclide distribution measurements from tree organs. Materials and Methods: A phantom composed of three-dimensional (3D) tree organs was constructed for the three upper whorls of the fir tree. A terminal bud was evaluated using Monte Carlo simulations for the absorbed dose rate of radionuclides in the tree organs of the whorls. Evaluation of the absorbed dose targeted 131I, 134Cs, and 137Cs, the main radionuclides subsequent to the FDNPP accident. The dose contribution from each tree organ was calculated separately using dose coefficients (DC), which express the ratio between the average activity concentration of a radionuclide in each tree organ and the dose rate at the terminal bud. Results and Discussion: The dose estimation indicated that the radionuclides in the terminal bud and bud scale contributed to the absorbed dose rate mainly by beta rays, whereas those in 1-year-old trunk/branches and leaves were contributed by gamma rays. However, the dose contribution from radionuclides in the lower trunk/branches and leaves was negligible. Conclusion: The fir tree model provides organ-specific DC values, which are satisfactory for the practical calculation of the absorbed dose rate of radiation from inside the tree. These calculations are based on the measurement of radionuclide concentrations in tree organs on the 1-year-old leader shoots of fir trees. With the addition of direct gamma ray measurements of the absorbed dose rate from the tree environment, the total absorbed dose rate was estimated in the terminal bud of fir trees in contaminated forests.

Cancer Risk Assessment Due to Natural and Fallout Activity in Some Cities of Pakistan

  • Ahad A.;Matiullah Matiullah;Bhatti Ijaz A.;Orfi S.D.
    • Journal of Radiation Protection and Research
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    • 제31권1호
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    • pp.1-7
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    • 2006
  • The measured mean activities of $^{226}Ra,\;^{232}Th,\;^{40}K\;and\;^{137}Cs$ in the soil of Bahawalpur, Bahawalnagar and Rahimyar Khan Bistricts were 32.9, 53.6, 647.4 and 1.8 Bq $kg^{-1}$. The average absorbed dose rate calculated from these activities was 74.3 nGy $h^{-1}$ and the mean annual effective dose rate was found to be 0.46 mSv $y^{-1}$. Absorbed doses to different body organs were derived from annual effective doses using tissue weighting factors. Radiation induced fatal cancer risks were assessed by using ICRP 60 Model. Estimations incurred 184deaths per year due to cancer.