• Journal of Radiation Protection and Research
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• 제47권4호
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• pp.204-213
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• 2022

Background: The accident at the Fukushima Daiichi nuclear power plant increased the level of anxiety related to the radioactive contamination of various foods sourced in Japan. Particularly, after the accident, the detection of artificial radionuclides in locally produced foods raised food safety concerns. In this study, the radioactivity concentrations and annual ingestions of ⁴⁰K and ¹³⁷Cs in food products commonly and frequently consumed by the general public were investigated, and the annual effective dose of each was evaluated. Materials and Methods: The 2016-2018 data from the Radiation Safety Management Report released by the Korea Nuclear Safety Technology Center was referenced for the evaluation of the amounts of ⁴⁰K and ¹³⁷Cs contained in food. Using the food-ingestion survey mentioned above as a reference, we selected 62 foods to include in our radioactivity concentration and dose assessment. We also developed a questionnaire and evaluated the responses from the subjects who answered the questionnaire. Results and Discussion: The radioactivity concentration of ¹³⁷Cs was found to be close to or below the level of minimum detectable activity. Additionally, the annual ingestion of 62 foods was 294.77 kg/yr, the effective doses from ⁴⁰K and ¹³⁷Cs were 136.4 and 0.163 μSv/yr, respectively. Conclusion: Thus, the findings confirmed that the effective dose from ⁴⁰K and ¹³⁷Cs in food tends to be lower than the effective dose limit of 1 mSv/yr suggested by the International Commission on Radiological Protection (ICRP) Publication 60. The questionnaire developed in this study is expected to be useful for estimating the annual effective dose status of Korean adults who consume foods containing ⁴⁰K and ¹³⁷Cs.

• 방사성폐기물학회지
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• 제21권3호
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• pp.371-381
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• 2023

Evaluating the effectiveness of the radiation protection measures deployed at the Centralized Radioactive Waste Management Facility in Ghana is pivotal to guaranteeing the safety of personnel, public and the environment, thus the need for this study. Radiagem^TM 2000 was used in measuring the dose rate of the facility whilst the personal radiation exposure of the personnel from 2011 to 2022 was measured from the thermoluminescent dosimeter badges using Harshaw 6600 Plus Automated TLD Reader. The decay store containing scrap metals from dismantled disused sealed radioactive sources (DSRS), and low-level wastes measured the highest dose rate of 1.06 ± 0.92 µSv·h^-1. The range of the mean annual average personnel dose equivalent is 0.41-2.07 mSv. The annual effective doses are below the ICRP limit of 20 mSv. From the multivariate principal component analysis biplot, all the personal dose equivalent formed a cluster, and the cluster is mostly influenced by the radiological data from the outer wall surface of the facility where no DSRS are stored. The personal dose equivalents are not primarily due to the radiation exposures of staff during operations with DSRS at the facility but can be attributed to environmental radiation, thus the current radiation protection measures at the Facility can be deemed as effective.

• 한국산학기술학회논문지
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• 제10권7호
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• pp.1760-1765
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• 2009

의료기관 핵의학과에서는 진단과 치료를 목적으로 방사성동위원소를 사용하므로 누구나 방사선피폭에 노출 될 위험이 있다. 일반적으로 방사선 작업종사자에 대한 피폭관리는 비교적 철저히 이루어지고 있으나 환자보호자 및 일반인에 대한 피폭관리는 소홀한 경향이 있다. 특히 방사성의약품을 투여한 환자들은 잠재적 선원이 되어 작업종사자외에 환자보호자 및 일반인에 대해 방사선피폭을 초래하므로 이로 인한 방사선피폭을 최소한으로 감소시킬 수 있도록 관리되어야 한다. 따라서 핵의학과 방사선피폭에 대한 관리실태를 파악하기 위하여 전국에 있는 대학병원 중 7개소에 대해 조사한 결과 환자이송요원, 환경미화원 등 수시출입자에 대해서 2 개소의 의료기관에서는 피폭선량평가 및 관리와 안전교육이 없었다. 또한 환자와 동행하는 보호자에 대한 통제와 관리는 7 개소 모두 허술하였는데 대기실에서 검사직전 환자로부터 흡수될 수 있는 평균 방사선량률은 25.60 ${\mu}$Sv/h로서 일반인에 대해 연간 선량한도를 초과하지 아니하는 범위 내에서 허용되는 20 ${\mu}$Sv/h를 초과하였다. 따라서 비록 아주 적은 피폭선량이 예상된다고 하더라도 수시출입자에 대한 철저한 피폭선량의 관리와 교육이 요구되며, 환자보호자 등을 보호하기 위해 환자와 가까이 하는 것을 통제하거나 환자를 격리할 필요가 있었다.

• Nuclear Engineering and Technology
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• 제49권8호
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• pp.1772-1777
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• 2017

Korean nuclear power plants (NPPs) periodically evaluate the radioactive gaseous and liquid effluents released from power reactors to protect the public from radiation exposure. This paper provides a comprehensive overview of the release of radioactive effluents from Korean NPPs and the effects on the annual radiation doses to the public. The amounts of radioactive effluents released to the environment and the resulting radiation doses to members of the public living around NPPs were analyzed for the years 2011-2015 using the Korea Hydro & Nuclear Power Co., Ltd's annual summary reports of the assessment of radiological impact on the environment. The results show that tritium was the primary contributor to the activity in both gaseous and liquid effluents. The averages of effective doses to the public were approximately on the order of $10^{-3}mSv$ or $10^{-2}mSv$. Therefore, even though Korean NPPs discharged some radioactive materials into the environment, all effluents were within the regulatory safety limits and the resulting doses were much less than the dose limits.

• Nuclear Engineering and Technology
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• 제49권3호
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• pp.598-608
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• 2017

A new radiation scale is proposed. With empathy toward the vast majority of people who are not well versed in radiation and related matters, and thus suffering from misunderstanding that breeds unnecessary fear of radiation, the aim of proposing a new radiation scale, radiation index (RAIN), is to put the general public at ease with the concept of radiation. RAIN is defined in dimensionless numbers that relate any specific radiation dose to a properly defined reference level. As RAIN is expressed in plain numbers without an attached scientific unit, the public will feel comfortable with its friendly look, which in turn should help them understand radiation dose levels easily and allay their anxieties about radiation. The expanded awareness and proper understanding of radiation will empower the public to feel that they are not hopeless victims of radiation. The correspondence between RAIN and the specific accumulated dose is established. The equivalence will allow RAIN to serve as a common language of communication for the general public with which they can converse with radiation experts to discuss matters related to radiation safety, radiation diagnosis and therapy, nuclear accidents, and other related matters. Such fruitful dialogues will ultimately enhance public acceptance of radiation and associated technologies.

• Nuclear Engineering and Technology
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• 제51권1호
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• pp.325-336
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• 2019

The activity concentrations of $^{226}Ra$, $^{232}Th$, and $^{40}K$ from 102 building materials samples were determined using a high-purity germanium (HPGe) detector. The activity concentrations were evaluated for possible radiological hazards to the human health. The excess lifetime cancer risks (ELCR) were also estimated, and the average values were recorded as $0.42{\pm}0.24{\times}10^{-3}$, $3.22{\pm}1.83{\times}10^{-3}$, and $3.65{\pm}1.85{\times}10^{-3}$ for outdoor, indoor, and total ELCR respectively. The activity concentrations were further subjected to RESRAD-BUILD computer code to evaluate the long-term radiation exposure to a dweller. The indoor doses were assessed from zero up to 70 years. The simulation results were $92{\pm}59$, $689{\pm}566$, and $782{\pm}569{\mu}Sv\;y^{-1}$ for indoor external, internal, and total effective dose equivalent (TEDE) respectively. The results reported were all below the recommended maximum values. Therefore, the radiological hazards attributed to building materials under study are negligible.

• 방사성폐기물학회지
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• 제16권4호
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• pp.473-478
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• 2018

원전 해체 공정 중 절단 및 용융작업에서 발생되는 방사성 에어로졸은 작업종사자의 호흡을 통해 내부 피폭을 유발하게 된다. 이에 따라 해체 중 방사성 에어로졸로 인한 작업종사자의 내부피폭 평가가 필요한 실정이다. 정확한 내부피폭평가를 위해서는 작업종사자의 작업환경 실측값이 필요하지만 실측에 어려움이 있을 시에는 국제방사선방호위원회(ICRP)에서 제시하는 섭취량 분율 및 입자 크기 등의 권고 값을 통해 내부피폭선량을 추정할 수 있다. 본 논문에서는 입자 크기의 선정은 ICRP에서 권고하는 작업종사자의 고려 입자 크기인 $5{\mu}m$을 적용하였다. 발생량의 경우, 불가리아의 Kozloduy 부지 내의 용융시설에서 발생 된 에어로졸의 포집량 데이터를 이용하여 섭취량을 산정하였다. 또한 이를 이용해 작업종사자의 체내 및 배설물에서의 방사능 수치를 계산하고 BiDAS 전산코드를 통해 내부피폭 평가를 수행하였다. Type M이 0.0341 mSv, Type S가 0.0909 mSv로 두 흡수 형태 각각 국내 연간 선량 한도의 0.17%, 0.45% 수준을 나타내었다.

• Environmental Analysis Health and Toxicology
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• 제24권3호
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• pp.203-211
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• 2009

A lesser degree of research is available with respect to indoor radon characteristics associated with occupants' exposure. The present study evaluated the radon levels in several public-access buildings or underground facilities, and their temporal variation in underground facilities. Radon measurements were conducted in 2005 and 2006, utilizing a continuous radon detector. A solid alpha detector (RAD7) was utilized to measure indoor radon levels. The mean radon concentrations obtained from the building or facilities were in a descending order: platforms of Daegu subway line 2, 2005 (32 $Bq/m^3$), hot-air bathroom (14 $Bq/m^3$), basement of office building (14 $Bq/m^3$), underground parking garage (14 $Bq/m^3$), underground shop (12 $Bq/m^3$), nursery (10 $Bq/m^3$), platforms of Daegu subway line 2, 2006 (9.0 $Bq/m^3$), platforms of Daegu subway line 1, 2006 (8.9 $Bq/m^3$), supermarket (7.9 $Bq/m^3$), hospital (7.3 $Bq/m^3$), and second-floor of office building (5.7 $Bq/m^3$). In general, underground-level facilities exhibited higher radon levels as compared with ground-level facilities. It was suggested that ventilation is an important parameter regarding the indoor levels of a subway. There was a decreasing or increasing trend in hourly-radon levels in a subway, whereas no trend were observed in a basement of office building. In addition, the radon levels in the subway lines 1 and 2 varied according to the platforms. The radon levels in the present study were much lower than those of previous studies. The average annual effective dose (AED) of radiation from indoor radon exposure was estimated to be between 0.043 and 0.242 mSv/yr, depending on facility types. These AEDs were substantially lower than the worldwide average AED (2.4 mSv/yr).

• 한국방사선학회논문지
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• 제15권6호
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• pp.803-811
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• 2021

본 연구에서는 공정 시뮬레이션 기술을 적용하여 조사유기응력부식균열 시험 작업자의 피폭량 평가를 하였다. 상용 공정 시뮬레이션 코드인 DELMIA Version 5를 사용하여 조사유기응력부식균열 분석 시험 설비, 핫셀 및 작업자를 작성하고 조사유기응력부식균열 시험 공정을 구현하였으며, 사용자 코딩을 통해 선량이 분포된 공간을 지나는 작업자의 누적 피폭량을 평가할 수 있도록 하였다. 작업자 모사를 위해 시험 공정별로 인체의 근골격계를 모방하여 약 200 개 이상의 자유도를 가지는 휴먼 마니킨 자세를 작성하였다. 작업자 피폭량 계산을 위하여 휴먼 마니킨 작업의 하위정보에 접근하여 자세 별 좌표, 시작 시간 및 유지 시간을 추출하였으며, 공간 선량 값과 자세 유지 시간을 곱하여 누적 피폭량을 계산하였다. 피폭량 평가를 위한 공간 선량은 MCNP6 Version 1.0을 사용하여 핫셀 내·외부 공간 선량을 계산하였으며, 계산된 공간 선량은 공정 시뮬레이션 도메인에 입력하였다. 공정 시뮬레이션을 이용한 피폭량 평가 결과와 전형적인 피폭량 평가 결과를 비교 분석한 결과, 상시 출입구역 내 일상 시험 작업에 대한 연간 피폭량은 각각 0.388 mSv/year 및 1.334 mSv/year로서 공정 시뮬레이션을 이용한 피폭량 평가 결과가 전형적인 방법의 피폭량 평가 결과 대비 70 % 낮게 예측되었다. 공간 선량 높은 구역에서 수행되는 특수작업에 대해서도 공정 시뮬레이션을 이용한 피폭량 평가를 수행하였으며, 피폭량이 높은 작업을 쉽게 선별할 수 있었고, 해당 작업의 휴먼 마니킨 자세와 공간 선량 가시화를 통해 직관적으로 작업 개선안을 도출할 수 있었다.

• Safety and Health at Work
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• 제12권2호
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• pp.174-183
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• 2021

Background: Toluene diisocyanate (TDI) is a highly reactive chemical that causes sensitization and has also been associated with increased lung cancer. A risk assessment was conducted based on occupational epidemiologic estimates for several health outcomes. Methods: Exposure and outcome details were extracted from published studies and a NIOSH Health Hazard Evaluation for new onset asthma, pulmonary function measurements, symptom prevalence, and mortality from lung cancer and respiratory disease. Summary exposure-response estimates were calculated taking into account relative precision and possible survivor selection effects. Attributable incidence of sensitization was estimated as were annual proportional losses of pulmonary function. Excess lifetime risks and benchmark doses were calculated. Results: Respiratory outcomes exhibited strong survivor bias. Asthma/sensitization exposure response decreased with increasing facility-average TDI air concentration as did TDI-associated pulmonary impairment. In a mortality cohort where mean employment duration was less than 1 year, survivor bias pre-empted estimation of lung cancer and respiratory disease exposure response. Conclusion: Controlling for survivor bias and assuming a linear dose-response with facility-average TDI concentrations, excess lifetime risks exceeding one per thousand occurred at about 2 ppt TDI for sensitization and respiratory impairment. Under alternate assumptions regarding stationary and cumulative effects, one per thousand excess risks were estimated at TDI concentrations of 10 - 30 ppt. The unexplained reported excess mortality from lung cancer and other lung diseases, if attributable to TDI or associated emissions, could represent a lifetime risk comparable to that of sensitization.