• 한국광학회지
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• 제28권1호
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• pp.16-21
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• 2017

고광도 섬광에 의하여 사람 눈에 미치는 영향을 체계적으로 이해하는 것은 고섬광의 사용상에나 눈의 보건의학적인 관점에서 큰 가치가 있다. 본 논문에서는 고섬광의 안전지표로서 노출제한거리를 제안하고, 섬광의 특성으로부터 노출제한 노출제한거리를 구하는 방법을 제시한다. 본 연구에서 고려한 고섬광에 대한 노출제한을 결정하는 요인은 망막에서 투영되는 열적 에너지이며 이는 망막의 열적위험을 나타내는 열적유효복사휘도로 표현된다. 고섬광의 노출제한거리는 열적 유효복사휘도 또는 광도와 광원 반경에 거의 비례하나 지속시간에는 거의 의존하지 않는다. 고섬광의 노출제한거리가 지속시간에 비례하지 않는다는 점은 눈에 미치는 영향이 노출되는 시간에 비례할 것이라는 기대와는 다른 중요한 발견으로 생각된다. 본 연구에서 제안된 노출제한거리는 고섬광의 연구개발과 활용에서 뿐만 아니라 눈을 보호하는 보건의학 분야에서도 안전지표로서 중요하게 활용될 것으로 기대된다.

• 한국산업보건학회지
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• 제32권1호
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• pp.10-20
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• 2022

Objectives: The aim of this study is to evaluate exposure levels of the extremely low frequency magnetic fields(ELF-MF) radiated from various electric facilities in Liquid Crystal Display(LCD) manufacturing processes. Methods: This study measured the exposure levels of personal and local ELF-MF for the electronic facilities installed in two LCD manufacturing companies. Samplers were installed around workers' waist during working hours to identify personal exposure levels, and direct reading equipment were located at 3 cm, 10 cm, and 30 cm away from the surface of the electronic facilities to measure local exposure levels. Average and maximum(ceiling) values were calculated for personal and local exposure levels. Results: Average and maximum of personal exposure levels for each worker were 0.56(mean) ± 0.02(SE) µT and 6.31 ± 0.75 µT, respectively. Statistical analyses of the study found that maximum of the personal exposure levels for engineers was significantly higher than that for operators since engineers spend more time near the electronic facilities for repairing. The range of maximum personal exposure levels was 0.50 ~ 43.50 µT and its highest level was equivalent to 4.35 % of ACGIH(American Conference of Governmental Industrial Hygienists) exposure limit value(1 mT). Maximum of local exposure levels was 8.18 ± 0.52 µT and the electronic facilities with higher exposure levels were roof rail and electric panel, which were not related to direct manufacturing. The range of maximum local exposure levels was 0.60 ~ 287.20 µT and its highest level was equivalent to 28.7 % of the ACGIH exposure limit value. Lastly, the local exposure levels significantly decreased as the measurement distance from the electronic facilities increased. Conclusions: Maximum of personal and local exposure levels did not exceed the exposure limit value of ACGIH. However, it is recommended to keep the workers as far as possible from the sources of ELF-MF.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.273-281
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• 2021

The radiological safety of the spent resin treatment facility with a¹⁴C treatment capacity of 1 ton/day was evaluated in terms of the external and internal exposure of worker according to operation scenario. In terms of external dose, the annual dose for close work for 1 h/day at a distance of more than 1 m (19.8 mSv) satisfied the annual dose limit. For 8 h of close work per day, the annual dose exceeded the dose limit. For remote work of 2000 h/year, the annual dose was 14.4 mSv. Lead shielding was considered to reduce exposure dose, and the highest annual dose during close work for 1 h/day corresponded to 6.75 mSv. For close work of 2000 h/year and lead thickness exceeding 1.5 cm, the highest value of annual dose was derived as 13.2 mSv. In terms of internal exposure, the initial year dose was estimated to be 1.14E+03 mSv when conservatively 100% of the nuclides were assumed to leak. The allowable outflow rate was derived as 7.77E-02% and 2.00E-01% for the average limit of 20 mSv and the maximum limit of 50 mSv, respectively, where the annual replacement of the worker was required for 50 mSv.

• The Korean Journal of Pain
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• 제33권1호
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• pp.73-80
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• 2020

Background: The aim of this study was to evaluate radiation exposure to the eye and thyroid in pain physicians during the fluoroscopy-guided cervical epidural block (CEB). Methods: Two pain physicians (a fellow and a professor) who regularly performed C-arm fluoroscopy-guided CEBs were included. Seven dosimeters were used to measure radiation exposure, five of which were placed on the physician (forehead, inside and outside of the thyroid protector, and inside and outside of the lead apron) and two were used as controls. Patient age, sex, height, and weight were noted, as were radiation exposure time, absorbed radiation dose, and distance from the X-ray field center to the physician. Results: One hundred CEB procedures using C-arm fluoroscopy were performed on comparable patients. Only the distance from the X-ray field center to the physician was significantly different between the two physicians (fellow: 37.5 ± 2.1 cm, professor: 41.2 ± 3.6 cm, P = 0.03). The use of lead-based protection effectively decreased the absorbed radiation dose by up to 35%. Conclusions: Although there was no difference in radiation exposure between the professor and the fellow, there was a difference in the distance from the X-ray field during the CEBs. Further, radiation exposure can be minimized if proper protection (thyroid protector, leaded apron, and eyewear) is used, even if the distance between the X-ray beam and the pain physician is small. Damage from frequent, low-dose radiation exposure is not yet fully understood. Therefore, safety measures, including lead-based protection, should always be enforced.

• 대한방사선기술학회지:방사선기술과학
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• 제45권2호
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• pp.159-164
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• 2022

The study developed a radiation dose measurement program in the radiology laboratory to measure how much exposure the students are exposed to during the radiology class, to request for the improvement and the revision of the current Nuclear Safety Act. The experimental program is shown in the following figure, and experiments were conducted to determine the degree of radiation exposure in the control room with a lead gown at a distance of 1 m, 2 m, and 1 m, and in a control room with a radiographic lead glass wall. The duration of the experiment was 3 months from April to June, when radiation imaging practice classes were conducted, and 128 hours of imaging practice per month were conducted. In order to find out the dose of radiation dose during radiology imaging practice class, the experiment was carried out from April to June for 3 months, and according to the program, the results of exposure dose were 0.34 mSv at 1 m distance, 0.01 mSv at shielding of lead gown at 1 m distance, 0.16 mSv at 2 m distance, and 0.01 mSv at control room with radiation lead glass wall. The exposure dose from the test results was much below the annual general public limit dose of 1 mSv. The restriction on the operation of the radiation equipment in the practice of the students is a regulation that infringes the right of students to learn, and amendments or exemptions of Nuclear Safety Act should be enacted to ensure that it does not violate the fundamental right to learn for students in radiology.

• 한국안전학회지
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• 제11권4호
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• pp.135-142
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• 1996

Prolonged in-plant personnel exposure to high noise levels results in permant hearing damage. There are no way to correct this hearing damage by treatment or use of hearing aids. Therefore, every employer is responsible for providing a workplace free of such hazards as excessive noise. This study was carried out to evalute and predict a given noise environment based on specific limit as the noise guarantee for a newly-founded petrochemical plant. The maximum total sound level should not exceed 85dBA in the work area, except where the area is defined as a restricted area and 70dBA at the plant boundary. Prediction of the noise levels within the plant area for a newly-founded petrochemical plant was achieved by dividing all plant area into 20m$\times$20m regular grid spaces and noise level inside the area or unit that in-plant personel exposure to high noise levels was estimated computed into 5m$\times$5m regular grid spaces. The noise level at the grid point that was propagated from each of the noise sources(equipments) computed using the methematical formula was defined as follows : $SPL_2$=$SPL_1-20log{\frac{r_2}{r_1}}$(dB) where $SPL_1$ =sound pressure level at distance $r_1$ from the source $SPL_2$=sound pressure level at distance $r_2$ from the source As a result, the equipments exceeded noise limit or irritaring noise levels were identified on the specific grid coordinates. As for equipments in the area that show high noise levels, appropriate counter-measures for noise control (by barriers, enclosure, silencers, or the change of equipments, for example) should be reviewed. Methods for identifying sources of noise applied in this study should be the model for prediction of the noise levels for any newly-founded plant.

• 핵의학기술
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• 제21권1호
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• pp.44-49
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• 2017

목적: 핵의학 검사를 시행한 병동 환자의 시간과 거리에 따른 방사선량률을 측정하여 방사성동위원소 투여를 받은 환자가 병동 간호사에게 미치는 피폭을 예측하고 실제 총 피폭량과 비교하여 보고자 한다. 대상 및 방법: 병동에서 근무하고 있는 간호사 14명을 대상으로 열형광 선량계와 광자극 선량계를 이용하여 방사선 피폭선량을 측정하였고 핵의학 검사를 시행한 환자 50명(PET/CT 20명, Bone scan 20명, Myocardial SPECT 10명)을 대상으로 방사성동위원소 투여 직후와 검사시행 직후에 표면, 50cm, 1m에서 외부 방사선량률을 측정하였다. 측정 결과를 바탕으로 유효반감기를 도출한 후 병동 간호사가 받을 수 있는 피폭량을 예측하였다. 그리고 열형광선량계와 광자극선량계로 측정된 병동 간호사의 실제 총 피폭량과 비교 하였다. 결과: 병동 간호사 14명을 대상으로 한 피폭선량 측정결과 평균값과 최대값은 각각 분기당 0.01 mSv, 0.02 mSv 이었고 핵의학 검사를 시행 받은 환자의 선량률은 표면, 50cm, 1m 거리 순으로 PET/CT는 $376.0{\pm}25.2{\mu}Sv/hr$, $88.1{\pm}8.2{\mu}Sv/hr$, $29.0{\pm}5.8{\mu}Sv/hr$ 이고 Bone scan은 $206.7{\pm}56.6{\mu}Sv/hr$, $23.1{\pm}4.4{\mu}Sv/hr$, $10.1{\pm}1.4{\mu}Sv/hr$이고 Myocardial SPECT는 $22.5{\pm}2.6{\mu}Sv/hr$, $2.4{\pm}0.7{\mu}Sv/hr$, $0.9{\pm}0.2{\mu}Sv/hr$이다. 또한 검사를 시행한 후 측정한 선량률은 표면, 50cm, 1m 거리 순으로 PET/CT는 $165.3{\pm}22.1{\mu}Sv/hr$, $38.7{\pm}5.9{\mu}Sv/hr$, $12.4{\pm}2.5{\mu}Sv/hr$ 이고 Bone scan은 $32.1{\pm}8.7{\mu}Sv/hr$, $6.2{\pm}1.1{\mu}Sv/hr$, $2.8{\pm}0.6{\mu}Sv/hr$이고 Myocardial SPECT는 $14.0{\pm}1.2{\mu}Sv/hr$, $2.1{\pm}0.3{\mu}Sv/hr$, $0.8{\pm}0.2{\mu}Sv/hr$이다. 위의 결과를 바탕으로 유효반감기를 도출한 후 검사종료 30분 후 원자력안전법에서 규정하는 일반인 선량한도까지 도달하는데 걸리는 시간을 반감기를 고려치 않고 보수적으로 계산하면 PET/CT는 표면, 50cm, 1m 거리 순으로 7.9시간, 34.1시간, 106.8시간이며 Bone scan은 40.4시간, 199.5시간, 451.1시간이고 Myocardial SPECT는 62.5시간, 519.3시간, 1313.6시간이다. 결론: 본 연구 결과에 의하면 병동 간호사는 일반인 선량한도 보다 훨씬 적은 피폭량을 받는 것으로 나타나, 실질적으로 판단할 때 핵의학 검사를 시행한 환자로 인하여 받는 피폭의 영향은 미미한 것으로 판단된다.

• 한국산업보건학회지
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• 제8권1호
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• pp.76-87
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• 1998

The concentration of welding fume was measured by 221 welders themselves in chassis frame workplace of the manufactory from February, 1, 1996 to May, 31, 1997. Welding parameters were the welding current and the distance between helmet and arc. Those two optimum conditions were proposed by excess probability analysis using logistic regression, so the best position in the workplace was proposed considering two factors to control the welding fume. The results are as followings; 1) The excess proability of welding fume TLV was over 99% in above 260 Amperes of welding current and also in below 30cm of distanced between helmet and arc. 2) The equation from logistic regression analysis using SPSS/PC+5.02 had the welding current as a independent variable and the excess of welding fume TLV as a dependent variable (p<0.05). Logit(welding fume TLV) = 0.1296 ${\times}$ wlding currnet - 28.8750 3) The equation from logistic regression analysis using SPSS/PC+5.02 had the distance between helmet and arc as a independent variable and the excess of welding fume threshold limit value a, a dependent variable (p<0.05). Logit (welding fume TLV) = -0.6809 ${\times}$ distance between helmet and arc +25.1665 4) Considering both cases or 2) and 3). the result equation is following. (p<0.05). Logit (welding fume TLV) = 0.1346 ${\times}$ welding current -0.3859 ${\times}$ distance between helmet and arc -15.7382 5) The excess probability of welding fume threshold limit value was 100% in above 240 Ampere of welding current. Thus, below 220 Ampere can be suggested to reduce the 40% number of welders who have a excess welding fume threshold limit value. 6) The excess probability of welding fume TLV was 100% in below 34cm of distance between helmet and arc. Thus, over 38cm can be suggested to reduce the 33% number of welders who have a excess welding fume TLV. 7) Considering both 5) and 6) cases, first of all, the best welding current can be 200 Ampere to have a below 15% of welding fume excess probability for the welders who works in distance of 34-37cm. Secondly, to have a below 30% excess probability of welding fume TLV, the working distance must be over 38cm in 220 Ampere and 32cm in 200 Ampere. 8) To reduce the average exposure concentration of welding fume ($8.21{\pm}5.83mg/m^3$), the movable local exhaust system equipped with flexible hoods can be used.

• 대한방사선기술학회지:방사선기술과학
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• 제45권4호
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• pp.347-353
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• 2022

In this study, the radiation dose rate was measured by time and distance and evaluated whether radiation dose rate was suitable for domestic and international discharge criteria. In addition, the radiation dose emitted from the patient was measured with a glass dosimeter to evaluate the exposure dose if the caregiver stays in the isolated ward by placing a humanoid phantom instead of the caregiver at a distance of 1 m from the patient, on the second day of treatment. After 23 hours of isolation, the radiation dose rates at a distance of 1 m were 20.54 ± 6.21 µSv/h at 2.96 GBq administration and 27.94 ± 12.33 µSv/h at 3.70 GBq administration. The radiation dose rates at a distance of 1 m were 25.90 ± 2.21 µSv/h when 2.96 GBq was administered and 34.22 ± 10.06 µSv/h when 3.70 GBq was administered after 18 hours of isolation. However, if the isolation period is short may cause unnecessary radiation exposure to the third person. The reading of the attached dosimeter from the morning of the second day of treatment until removal was 0.01 to 0.95 mSv, which is a surface dose determined by the International Commission on Radiation Units and Measurements. And the depth dose was 0.01 to 0.99 mSv. On the second day of treatment, even if the patient caregivers stayed in the isolation ward, the exposure dose of the patient family did not exceed the effective dose limit of 5 mSv recommended by the ICRP and NCRP.

• 한국방사선학회논문지
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• 제14권3호
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• pp.279-287
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• 2020

방사선은 의료, 연구, 산업 등 다양한 분야에서 활용되고 있어 방사선 이용기관 및 방사선작업종사자의 수가 증가하고 있으며, 방사선 관련 피폭 사고도 발생함에 따라 방사선방호 및 안전에 대한 관심이 증가하고 있다. 이에 원자력안전법에서는 방사선원을 이용하는 장소에 대해서는 선량한도를 초과하지 않도록 하기 위해 차폐물을 설치하도록 규정하고 있다. 특히, 고정 설치된 차폐시설이 없는 곳에서 방사선투과검사 작업 수행 시, 일정한 선량율을 기준으로 작업장 출입 및 일반인 접근 여부를 감시하고 있다. 하지만, 고정 설치된 차폐시설 없는 곳에서의 방사선투과검사 작업 허가 신청 시, 방사선관리구역 및 (일반인) 감시구역거리 및 해당 거리에서의 피폭선량 계산에 고려해야 할 인자들은 법적으로 규정되어 있지 않다. 이에 본 연구에서는 방사선방호용 도구(납 담요, Collimator)의 특성(규격, 두께 등), 사용 선원 등을 입력 시, 자동으로 방사선관리구역 및 (일반인) 감시구역 거리와 비용을 산정해 주는 Excel model을 개발하였다. 이후 특정 가정을 바탕으로 방사선방호용 도구 두께에 따른 피폭선량 및 거리 변화율을 분석한 결과, 방사선방어용 도구의 두께가 증가함에 따라 방사선관리구역의 거리는 감소하였으나, 납 담요 두께가 25 mm, Collimator의 두께가 21.5 mm 이상부터는 거리의 변화율이 낮았다. 따라서, 해당 두께 이상의 방사선방어용 도구를 사용하고도 방사선관리구역 및 (일반인) 감시구역에서의 피폭선량이 높은 경우, 방사선방어용 도구 이외의 요소를 변화시켜 피폭선량을 낮추어야 할 것으로 예상된다. 또한, 본 연구에서는 1) 피폭선량 계산 시, 산란성 및 Build up 등을 고려하지 않은 점, 2) 납 담요 및 Collimator의 실제 모양이 아닌 직육면체와 중심이 빈 원기둥 모양으로 가정 등으로 인해 실제 피폭선량과 차이가 있다는 한계점이 있었다. 따라서, 향후 앞선 한계점들을 고려하면서 실제 작업환경에 대한 자료를 활용하여 연구를 수행한다면, 실제 작업환경을 바탕으로 방사선관리구역 거리 및 피폭선량 등에 대한 Database 구축이 가능할 것으로 예상된다.