• Journal of the Korean Society of Radiology
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• v.16 no.3
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• pp.357-363
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• 2022

This study aims to improve the safety inspection awareness of occupational exposure and help radiation safety management by analyzing radiation exposure doses by occupational type of radiation related-workers and radiation workers. Radiation-related workers and radiation workers were classified into three occupations (radiological technologist, doctors, and nurses). A nominal risk coefficient based on ICRP 103 was used to calculate the probability of causing side effects of the lungs due to exposure doses. As a result of analyzing the exposure dose of all workers for one year, the exposure dose of radiological technologist among radiation-related workers was 1.63 ± 2.84 mSv, doctors 0.12 ± 0.22 mSv, and nurses 0.59 ± 1.08 mSv. The one-year deep dose for radiation workers was 2.44 ± 3.30 mSv for radiological technologists, 0.19 ± 0.26 mSv for doctors, and 0.12 ± 0.00 mSv for nurses. Due to this dose, the probability of causing side effects in the lungs was 1.2 per 100,000 radiological technologist, 0.096 doctors, and 0.06 nurses. In this study, it is believed that the probability of side effects on lungs by occupation of radiation exposure dose will be studied and used as useful data for radiation safety management in relation to probabilistic effects in the future.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.919-924
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• 1995

사람이 숨을 쉬는 동안에 대기중에 포함된 C-14이 인체내에 흡수되는 경로를 살펴보았으며 이로부터 호흡경로를 통한 C-14의 체내 흡수량을 평가하였는데, 호흡중 C-14이 체내에 흡수되는 속도는 다음과 같이 구해졌다. $Q_{i}$(mBq/min)=7.250C$_{a.in}$ - 0.87 여기서 $C_{a,in}$ 은 공기중에 포함된 이산화탄소중의 C-14 농도(mBq/$m\ell$$CO_2$)이다. 이를 토대로 백그라운드 준위보다 약 10,000배 높은 작업환경(400 Bq/$m^2$)에서 8시간 동안 방사선작업을 수행하였을 경우 방사선 작업자는 일반인에 비해 약 4,100 Bq의 C-14 방사능을 추가로 섭취하게 되고, 이로 인해 작업자가 받게 될 체내 피폭선량은 약 0.06 mrem이었다.

• 대한방사선방어학회:학술대회논문집
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• 2009.11a
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• pp.220-221
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• 2009

• 대한방사선방어학회:학술대회논문집
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• 2011.04a
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• pp.62-63
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• 2011

• 대한방사선방어학회:학술대회논문집
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• 2009.04a
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• pp.290-291
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• 2009

• Journal of radiological science and technology
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• v.34 no.3
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• pp.221-229
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• 2011

This paper reports a series of job analyses to develop a curriculum for radiologic technologists by using DACUM (Development A Curriculum). With this method, the jobs of radiologic technologist were divided into 8 duties and 59 tasks. The results showed that the most important duty was 'exposure management (M=4.72)', the most difficult duty was 'radiation therapy (M=4.29)', and the most frequently performed duty was 'radiation examination (M=4.19)' respectively. In addition these results were compared with the current curriculum. It turned out that there are quite differences between the school education and actual work. For example, 'patients care' duty was identified as the main job but only 57.1% of the schools offer related courses. The current curriculum focused on the theory for the radiologic technologist is not sufficient to perform the field operation.

• Proceedings of the Korean Institute of Navigation and Port Research Conference
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• 2017.11a
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• pp.54-55
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• 2017

본 연구는 항만에 설치된 방사선감시기의 검색기능 극대화를 위하여 방사선감시기의 검색환경을 분석하고 물류흐름 관점에서 운영환경 개선방안 도출을 목적으로 한다. 본 연구 목적 달성을 위해 원자력안전위원회에서 제시한 방사선 위험화물의 수입 물동량 분석을 수행하여 방사선감시기 설치 타당성을 확보하였다. 문헌조사와 현장 전문가 인터뷰를 통해 항만의 방사선감시기 설치환경 및 운영에 따른 물류 장애요인을 분석하였다. 또한, 항만 내 방사선감시기 설치가 가능한 위치를 3단계(본선하역작업, 야드 이송 및 적재 작업, 게이트 반출)로 구분하여 각 위치별 장 단점을 분석하고 최적의 감시기 설치 위치를 도출하였다. 연구결과, 감시기 설치 위치 단계별 비용, 물류흐름, 관리 운영적 측면을 고려하였을 때, 게이트 반출 단계가 방사선 감시기 설치를 위한 최적위치로 적합한 것으로 확인하였다. 방사선감시기의 운영최적화 방안으로는 첫째, 반출 게이트 내부의 2차 검색부지 확보를 통해 게이트 통과 전 방사선감시기를 통한 화물 검색이 이루어질 수 있도록 해야 한다. 둘째, 화물인도지시서(Delivery Order: D/O)를 활용한 신속한 화물정보 파악을 통해 물류흐름의 방해요인을 제거 할 수 있음을 알 수 있다.

• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.356-357
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• 2011

• The Journal of the Korea Contents Association
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• v.9 no.6
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• pp.247-255
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• 2009

This study aims to provide basic data for establishing the safety and health plan by investigating the exposure conditions in the facilities registering business about handling radiations and radioactive isotopes in Korea. dose levels(working space, worker location) of the workers in 153 facilities were measured using surveymeter, and individual exposure concentration[(shallow dose(SD), depth dose(DD)] in 27 facilities using thermal luminescence dosimeter(TLD). In accordance with the measurement results by business type[fire fighting prevention business(FFPB, n=10), financial insurance business(FIB, n=3) and other facilities(n=140)] using surveymeter, those three business type groups showed difference (p<0.000). Dose levels of worker location for FFPB and FIB were significantly higher than 10.0 ${\mu}Sv$/hr, the allowable standard for radiations and radioactive isotopes, and they were higher 109.3 times(p<0.000) and 187.5 times(p<0.000) than those in other facilities. The concentration of TLD[FFPB(n=10), other facility (n=17)] in DD of FFPB was significantly higher than that in other facility(p=0.05). In accordance with the analysis result on relationship between surveymeter and TLD, the dose on working space and worker location(r=0.406, p<0.05), worker location dose and SD(r=0.453, p<0.05), worker location dose and DD(r=0.553, p<0.01), and SD and DD(r=0.927, p<0.001) had all related each other. It is urgently required to change FFPB and FIB from the facilities requiring registration for handling radiations and radioactive isotopes to the facilities that shall get permission for handling radiations and radioactive isotopes by reestablishing the legal administration area, for safety and health of radiation occupants.

• Journal of Radiation Protection and Research
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• v.23 no.3
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• pp.149-157
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• 1998

An analysis has been performed to estimate the additional number of workers and the additional collective dose in man-cSv which would be required, nuclear industry-wide as a result of reducing individual dose limit. This analysis can be extended to the reduction in the dose limits recommended by ICRP Publ.60 and BEIR V report as well as the proposed dose limits by regulatory authorities. An industry-wide database was employed in the analysis based on a summary of industry-wide occupational radiation exposure compiled by the Korea Radioisotope Association. Correlation model was employed to compute the affects of setting specific annual individual dose limits. In this study, we have addressed worker non-productivity while in the radiation environment on a parametric or 'sensitivity analysis' basis. This alleviates the need for developing such data underlying a summation of many individual tasks at many nuclear facilities. It has the advantage that very low non-productivity assumptions can readily be defended as conservative, in that it is difficult to approach such low worker non-productivity factors even in the best of environments in any industry. On a per facility basis, for calendar year 1997, the number of workers required would be increased from 231 workers to 269 workers and collective man-cSv dose would be also increased by approximately fourteen percent if the individual dose limit was reduced to 2 cSv/y and an individual worker non-productivity fraction of 0.1 is assumed.