• Nuclear Engineering and Technology
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• 제55권8호
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• pp.3046-3053
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• 2023

Radon is a naturally occurring carcinogenic agent, poses a serious health hazard when inhaled or ingested in significant amounts. The water of the Padma river will be used as a tertiary coolant for the soon-to-be-commissioned 'Rooppur Nuclear Power Plant'. Hence, it is important to assess the radiological status of the river prior to the commission of this power plant. Therefore, for the first time, 25 samples of water were collected from various locations of the Padma River and analyzed for radon concentration using the RAD H₂O (DURRIDGE) radon monitoring device. The radon concentrations were found in the range from 0.077 ± 0.036 to 0.494 ± 0.211 Bq/L with a mean of 0.250 ± 0.093 Bq/L. All the concentrations were found to be below the recommended limits of WHO (100 Bq/L) and USEPA (11.1 Bq/L). The mean annual effective dose due to the radon exposure via inhalation and ingestion pathways were 0.638 µSv/y and 0.629 µSv/y, respectively, which were all well below the annual effective dose recommended by WHO (0.1 mSv/y). Since Bangladesh lacks a national safety limit of radon in water, this pioneering study provides baseline data on radon levels for the environment around Rooppur Nuclear Power Plant.

• 대한방사선기술학회지:방사선기술과학
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• 제34권2호
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• pp.105-116
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• 2011

두경부(Head & Neck) CT(Computed Tomography)검사에서 환자가 받는 피폭선량 측정을 위하여 인체등가물질로 만든 Rando phantom과 유리선량계를 이용하여 두경부 검사에 따른 환자의 흡수선량의 변화를 실험을 통하여 연구하였다. 인체두부모형을 안와신경(optic nerve), 교뇌(pons), 소뇌(cerebellum), 갑상선(thyroid)으로 나누어, 두경부(Head & Neck) 부위의 검사를 단독검사(Brain, 3D Facial, Temporal, Brain Angiography, 3D Cervical Spine)와 복합검사(Brain+Brain Angiography, Brain+3D Facial, Brain+Temporal, Brain+3D Cervical spine, Brain+3D Facial+Temporal, Brain+3D Cervical Spin+Angiography)로 구분하여 유효선량의 변화를 실험한 후 결과를 측정하였다. 단순 Brain검사와 Brain Angio검사에는 optic nerve에 유효 선량이 높게 분석되었으며, 또한 Temporal검사에는 Pons에, 3D facial 검사와 3D Cervical Spin검사에는 thyroid의 유효선량 값이 높게 나타났다. 복합적으로 이루어는 검사 중 두경부의 Brain+Brain Angio의 검사는 cerebellum의 부위, Brain+3D facial 검사와 Brain+3D Cervical Spin의 복합검사는 thyroid의 부위, Brain+Temporal의 검사에는 pon's 부위 유효 선량 값이 높게 나타났다. Brain +3D facial +Temporal의 복합검사와 Brain+3D Cervical Spin+Angio의 복합검사는 thyroid의 부위에 유효 선량 값이 높게 분석 되었다. 본 연구 결과 Brain+3D Cervical Spin+Brain Angio 복합검사인 경우의 유효 선량은 2.51858 mSv로 일반인의 연간 유효선량한도 1 mSv의 피폭을 초과하는 결과가 나왔다. 또한, Brain 단순 검사 시 optic nerve는 0.31312 mSv의 유효선량으로 향후 방사선학 검사가 이루어질 경우, 두경부의 일반인의 연간 유효선량을 훨씬 초과할 것이라 사료된다. 따라서 진료의 필요성에 의해서 시행되는 CT검사일지라도 질환 병변의 특성에 맞게 CT촬영조건 변화를 주면서 환자의 피폭선량을 최소한으로 할 수 있는 다양한 검사방법의 연구가 필요하다고 사료된다.

• 방사선산업학회지
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• 제17권2호
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• pp.161-172
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• 2023

Coal-fired power plants handle large quantities of coal, one of the most prominent NORM, and the coal ash produced after the coal is burned can be tens of times more radioactive than the coal. Workers in these industries may be exposed to internal exposure by inhalation of particles while handling NORM. This study evaluated the size, concentration, particle shape and density, and radioactivity concentrations of airborne suspended particles in the main processes of a coal-fired power plant. Finally, the internal radiation dose to workers from particle inhalation was evaluated. For this purpose, airborne particles were collected by size using a multi-stage particle collector to determine the size, shape, and concentration of particles. Samples of coal and coal ash were collected to measure the density and radioactivity of particles. The dose conversion factor and annual radionuclide inhalation amount were derived based on the characteristics of the particles. Finally, the internal radiation dose due to particle inhalation was evaluated. Overall, the internal radiation dose to workers in the main processes of coalfired power plants A and B ranged from 1.47×10^-5~1.12×10^-3 mSv y^-1. Due to the effect of dust generated during loading operations, the internal radiation dose of fly ash loading processes in both coal-fired power plants A and B was higher than that of other processes. In the case of workers in the coal storage yard at power plants A and B, the characteristic values such as particle size, airborne concentration, and working time were the same, but due to the difference in radioactivity concentration and density depending on the origin of the coal, the internal radiation dose by origin was different, and the highest was found when inhaling coal imported from Australia among the five origins. In addition, the main nuclide contributing the most to the internal radiation dose from the main processes in the coal-fired power plants was thorium due to differences in dose conversion factors. However, considering the external radiation dose of workers in coal-fired power plants presented in overseas research cases, the annual effective dose of workers in the main processes of power plants A and B does not exceed 1mSv y^-1, which is the dose limit for the general public notified by the Nuclear Safety Act. The results of this study can be utilized to identify the internal exposure levels of workers in domestic coal-fired power plants and will contribute to the establishment of a data base for a differential safety management system for NORM-handling industries in the future.

• 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.

• 방사선산업학회지
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• 제8권2호
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• pp.123-132
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• 2014

After the nuclear accident of the Fukushima Dai-ichi Nuclear Power Plants (FDNPPs) on 11 March 2011, a large amount of radioactive materials has been released into the atmosphere and the ocean. A compartment model is used to evaluate the circulation characteristics and the spatiotemporal concentration distributions of radionuclides in the ocean. In the comparison with observed concentrations of $^{137}Cs$ in seawater, calculated concentrations by the compartment model were well agreed with them. On the basis of these results, we performed evaluation of the effective dose and the cancer risk. In the early stage of the accident, the effective doses from ingestion of the seafood near the Fukushima region were much higher than 1 mSv which is the value of the annual effective dose limit to individual recommended by the International Commission on Radiological Protection (ICRP). However, the effective doses by ingestion of the seafood decreased below 1 mSv as distance from the FDNPPs increased and time passed. In addition, it was estimated that the cancer risks by intake of the contaminated marine products were less than natural occurrence probability of cancer. Consequently, it was inferred that the health risk due to the $^{137}Cs$ was low after since mid-term period of the accident.

• Journal of Radiation Protection and Research
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• 제16권1호
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• pp.1-13
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• 1991

국내 12개 지역의 340여 실내에서 측정한 라돈농도로부터 단순한 수학적 폐선량 평가모형을 이용하여 주민의 실효선량당량을 평가하였다. 수동적 시간적분형 CR-39 라돈컵으로 1990년 4월부터 10월까지 $3{\sim}4$개월 동안 측정 한 실내의 라돈농도는 지역별로 $33.82{\sim}61.42 Bq/m^3$(평균 : $48.90 Bq/m^3$)의 분포를 보였으며, 이로 인한 라돈자핵종의 평형등가라 돈농도$(EEC_{Rn})$는 라돈과 자핵종간의 평형인자의 값 0.4를 적용했을 때 $13.53{\sim}24.57Bq/m^3$(평균 : $19.55 Bq/m^3$)으로 예상되었다. 국제방사선방어위원회의 폐모형에 근거한 본 연구의 폐선량 평가모형에서 유도된 단위 평형등가라돈농도의 피폭당 실효선량당량환산 인자는 $1.07{\times}10^{-5}\;mSv/Bq\;h\;m^{-3}$으로 국제방사선방어위원회나 국제연합 방사선영향평가 과학위원회(UNSCEAR)에서 권고한 값과 잘 일치하였다. 동 선량환산인자와 CR-39 라돈 컵으로 측정 한 실내 의 평균 평형등가라돈농도를 년간 $0.75 m^3/h$의 호흡율로 호흡한 것으로 가정했을 때, 주민이 받는 년평균 폐선량당량 및 실효선량당량은 갹각 20.90 mSv 및 1.25 mSv인 것으로 평가되었다. 동 피폭선량은 국제연합(UNSCEAR)에서 1988년에 발표한 일반인의 년평균 자연방사선피폭 실효선량당량인 2.40mSv의 거의 50%에 상당하였다.

• Journal of Radiation Protection and Research
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• 제12권2호
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• pp.37-50
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• 1987

The exposure of the population in the United States to ionizing radiation has recently been evaluated by the National Council on Radiation Protection and Measurements (NCRP). This was done by constituting six organizational groups to address various phases of the work and the results of this work are summarized in this article. The article is based on the report, by the same title, which is scheduled for publication by the NCRP in September, 1987. The six organizational groups are titled Radiation Exposure from Consumer Products, Natural Background Radiation, Radiation Associated with Medical Examinations, Radiation Received by Radiation Employees, Public Exposure from Nuclear Power, and Exposure from Miscellaneous Environmental Sources. These titles are descriptive of the subject areas covered by each of these separate groups. The data evaluated are for the years 1977-1984 with the majority of the data being for the period 1980-1982. Summary information is presented and discussed for the number of people exposed to given sources, the effective dose equivalent, the average effective dose equivalent to the U.S. population, and the genetically significant dose equivalent. The average annual effective dose equivalent from all sources to the U.S. population is approximately 3.6 mSv (360 mrem). Exposures to natural sources make the largest contribution to this total. Radon and radon decay products contribute 2.0 mSv (200 mrem) whereas the other naturally occurring radionuclides contribute 1.0 mSv (100 mrem). Among man-made or enhanced sources, medical exposures make the largest additional contributions, namely 0.39 mSv (39 mrem) for diagnosis and 0.14 mSv (14 mrem) for nuclear medicine. It was not possible to evaluate exposures for therapy. Most of the other sources of population exposure, including nuclear power and consumer products, are minor. A possible exception would be the use of tobacco products. These exposures are discussed in relation to a negligible individual risk level of $10{\mu}Sv/y$ (1 mrem/y). The NCRP considers exposures below the negligible individual risk level as trivial and as such should be dismissed.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.291-298
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• 2001

The designed release rate of liquid effluents from radwaste treatment system should be calculated and evaluated during normal operation, including anticipated operational occurrence and be assured that the release concentration and off-site dose at unrestricted area do not exceed the limits of regulation. The expected annual release rate and off-site dose for the currently operating nuclear power plants in Korea had been calculated and evaluated using PWR-GALE and LADTAP-II which was based on USNRC Regulatory Guide 1.109. Recently, the MOST Notice 2001-2 related to release concentration and off-site dose at unrestricted area was revised to reflect the concept of ICRP-60. It is necessary for KORI 3&4 to re-calculate the release concentration and off-site dose and to compare these results with the limits of regulation. As the results of assessment, we confirmed that the release concentrations were less than its limits of MOST Notice 2001-2 and the off-site dose at unrestricted area using K-DOSE60 was 3.61E-03 mSv/yr to the age of five for the effective dose, and 4.10E-2 mSv/yr to thyroid of the age of five for the organ equivalent dose. We also confirmed the off-site dose was within the limits of MOST Notice 2001-2. Therefore, the release concentration and off-site dose re-evaluated at unrestricted area in KORI 3&4 were well below the regulation limits of MOST Notice 2001-2.

• Nuclear Engineering and Technology
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• 제25권3호
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• pp.437-446
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• 1993

가동중 원자력 시설에서 방출되는 방사성 핵종의 년간 인체 흡수량을 보다 현실적으로 평가하기 위한 계산 모델을 수립하였다. 이 모델을 적용하기 위해서는 평가년도 중에 소비되는 식량 및 사료 작물의 수확년도와 실제 가동된 전기간내 매년의 공기중 및 수중 평균농도가 고려되어야 한다. 한국인에 대한 평형 섭식경로 평가코드인 KFOOD 코드를 수립된 계산모델에 따라 수정하였다. 가상적인 10 년간의 균일방출에 대하여 개선된 방식, KFOOD 방식, 그리고 또다른 현존 방식에 의한 평가가 이루어 질 수 있도록 입력 데이타 파일을 차례로 변경하여 수정된 코드를 실행시키고 세가지 결과들을 비교하였다. Mn-54, Co-60, Sr-90, I-131 그리고 Cs-137의 흡수를 통한 한국 성인의 년간 예탁실효선량을 개선된 방식으로 계산한 결과는 KFOOD 방식에 비해 각각 11, 2, 5, 60, 3%정도 낮았다. 개선된 방식에 따른 평가에 있어서는 Sr-90을 제외한 핵종들의 인체흡수에 대해서는 엽면흡수 경로의 기여가 훨씬 컸으나 Sr-90의 경우에는 뿌리흡수 경로의 기여가 훨씬 컸다.

• 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).