• 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.

• Journal of Microbiology and Biotechnology
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• 제21권1호
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• pp.100-108
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• 2011

A method for the rapid detection and quantification of Newcastle disease virus (NDV) produced in an animal cell culture-based production system was developed to enhance the speed of the NDV vaccine manufacturing process. A SYBR Green I-based real-time RT-PCR was designed with a conventional, inexpensive RT-PCR kit targeting the F gene of the NDV LaSota strain. The method developed in this study was validated for specificity, accuracy, precision, linearity, limit of detection (LOD), limit of quantification (LOQ), and robustness. The validation results satisfied the predetermined acceptance criteria. The validated method was used to quantify virus samples produced in an animal cell culture-based production system. The method was able to quantify the NDV samples from mid- or late-production phases, but not effective on samples from the early-production phase. For comparison with other quantifiable methods, immunoblotting, plaque assay, and tissue culture infectious dose 50 ($TCID_{50}$) assay were also performed with the NDV samples. The results demonstrated that the real-time RT-PCR method is suitable for the rapid quantification of virus particles produced in an animal cell-culture-based production system irrespective of viral infectivity.

• 대한방사선기술학회지:방사선기술과학
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• 제41권5호
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• pp.479-485
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• 2018

Radiologic technologists working at the second and third medical institutions are classified as radiation-related workers and radiation workers according to their working departments, and are subject to double regulation by the Ministry of Health and Welfare and the Nuclear Safety Commission. We will try to understand the system of dualization and to understand the investigation of recognition. The dualized system of radiation-related workers and radiation workers includes the difference in name and terminology, the effective dose limit, the maintenance education and training of radiologic technologists, the period of medical examination, the radiation zone, dose of the woman whose pregnancy is confirmed in radiologic technologists, the qualification criteria of the safety officer, and the period of the regular inspection of the radiological equipment. In the questionnaire survey on the dualization system, there were various items showing significant differences between the radiation-related workers and radiation workers Overall, the radiation workers were more aware of the radiation workers' education and related terms than the radiation-related workers.

• 방사선산업학회지
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• 제10권4호
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• pp.205-210
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• 2016

This study was conducted to evaluate the combined effect of gamma irradiation and different conditions (vacuum packaging, antioxidant and freezing) on the microbiological and sensory characteristics of freeze dried Manila clam porridge (MCP) for immuno-compromised patient food. MCP can be sterilized at 1 kGy to 10 kGy. The initial counts of total aerobic bacteria and yeast molds in the non-irradiated MCP were $2.4{\pm}0.5$ and $1.2{\pm}0.3{\log}\;CFU\;g^{-1}$, respectively, but gamma irradiation significantly decreased the total aerobic bacteria to below the detection limit ($1{\log}\;CFU\;g^{-1}$) (5 kGy). Moreover, gamma irradiation effectively eliminated yeasts/molds at dose below than 1 kGy. However, gamma irradiation accelerated the increase of lipid oxidation and therefore, decreased the sensory characteristics of MCP as irradiation dose increased. To improve the sensory qualities of gamma irradiated MCP, combination treatment (vacuum packaging, 0.1% vitamin C) were applied. There was no significant difference in the overall acceptance scores between the combined-treatment sample (5.6 points) and the non-irradiated samples (6.0). The results indicate that combination treatment (vacuum packaging, 0.1% vitamin C) may help to maintain the quality of MCP. Therefore, it considered that irradiation of MCP with combined treatment and this is an effective method for the consumption as a special purpose food such as for space travel or immuno-compromised patients.

• 자원환경지질
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• 제49권4호
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• pp.301-314
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• 2016

국내에서 발생한 폐밀봉선원은 현재 한국원자력환경공단 폐기시설에 임시 보관 중에 있으며 향후 중 저준위 방사성 폐기물 처분시설에 처분될 예정이다. 본 연구에서는 폐밀봉선원의 최적 처분방안 수립에 앞서 폐밀봉선원 처분시 폐쇄후 예비안전성평가를 수행하였다. 폐밀봉선원이 표층처분시설 또는 동굴처분시설에 처분되는 것으로 가정하였으며, GoldSim 전산코드를 사용하여 결정집단의 개인 피폭선량을 계산하였다. 평가결과 정상 시나리오시 최대 피폭선량은 두 가지 처분방식에 대해 약 $1{\times}10^{-7}mSv/yr$으로 나타났으며 이는 규제치인 0.1 mSv/yr에 대비하여 장기적으로 충분한 안전성을 확보할 수 있는 것으로 판단된다. 우물시나리오 시 최대 피폭선량은 표층처분시설에서 규제치인 1 mSv/yr를 초과하였으며 이는 $^{226}Ra$, $^{210}Pb$($^{226}Ra$의 딸핵종) 및 $^{237}Np$($^{241}Am$의 딸핵종)에 기인한 것으로 확인되었다. 동굴처분시설의 경우, 모든 핵종의 최대 피폭선량이 법적 규제치를 만족하나 $^{14}C$ 및 $^{237}Np$($^{241}Am$의 딸핵종)에 의한 피폭선량이 규제치 대비 10%를 초과하는 상대적으로 높은 값을 나타내는 것으로 확인되었다. 처분시설 폐쇄후 주민의 피폭선량은 반드시 법적 규제치 이하로 유지되어야 하므로 규제치를 초과 또는 이에 근접한 피폭선량을 유발하는 핵종인 $^{14}C$, $^{226}Ra$ 및 $^{241}Am$를 각 처분방식에서 제한할 필요가 있으며 안전한 영구 처분을 위한 처분전 관리가 요구된다.

• 대한방사선기술학회지:방사선기술과학
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• 제37권3호
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• pp.177-185
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• 2014

자동노출제어를 이용한 X선 흉부촬영에서 AEC 위치를 알 수 있도록 고안 된 AEC 표지자 사용에 따른 환자 피폭선량 감소 효과에 대하여 알아보고자 하였다. 흉부전용 디지털 X선 장비(DRS, LISTEM, Korea)를 이용하여 흉부촬영 검사를 하여야 하는 성인 남녀 880명을 대상으로 하였다. 대상환자 모두에서 자동노출제어(이온 전리조 양측 상단 2개 사용) 사용하여 촬영하였다. 조사야 크기는 $17{\times}17inch$, 관전압은 120kVp, 촬영거리는 180cm로 설정 하였다. 대조군 440명은 Detector 내에 양측 폐가 위치하도록 하여 촬영하였고, 실험군 440명은 이온 전리조 위치를 방사선사가 알 수 있도록 표지자를 만든 후 이온 전리조 위치에 양측 폐를 위치 할 수 있도록하여 촬영하였다. 모든 환자의 나이, 몸무게, 키와 DAP 값을 측정 하였으며, PCXMC2.0을 이용하여 환자의 유효선량 값을 계산 하였다. 대조군 440명(M:F=245:195)의 평균 나이는 53.9세였으며, 평균 BMI는 23.4였다. BMI 분포는 저체중 35명, 정상 279명, 과체중 106명, 비만 20명이었고, 평균 DAP는 $223.56mGycm^2$, 평균유효선량은 0.045mSv 였다. 실험군 440명(M:F=197:243)의 평균 나이는 53.7세 였고, 평균BMI는 22.7이었다. BMI 분포는 저체중 34명, 정상 316명, 과체중 85명, 비만 5명이었고, 평균 DAP는 $207.36mGycm^2$, 평균유효선량은 0.041mSv 였다. 평균유효선량은 실험군이 대조군에 비해 0.004mSv(9.7%) 감소하였다. 실험군 유효선량 표준편차의 2배인 0.056mSv 이상의 과다피폭을 받은 환자는 실험군에 비하여 대조군에서 많았다 (65명(14.7%) 대 19명(4.3%), p=0.006, t-test). 자동노출제어를 이용한 X선 흉부촬영에서 환자에 맞는 정확한 선량을 위해서는 이온 전리조 위치와 검사부위를 일치 시켜야 하며 따라서 이온 전리조 위치를 알 수 있도록 고안한 표시 방법은 환자가 받을 수 있는 불필요한 방사선 피폭을 줄일 수 있는 방법이다.

• 핵의학기술
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• 제18권2호
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• pp.57-61
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• 2014

국내 갑상선암 환자의 발병률이 증가함에 따라 방사성요오드 치료가 필요한 환자가 증가하고 있다. 방사성 요오드 치료에 이용되고 있는 캡슐용기들 중 1.1 GBq과 5.5 GBq의 국산제품에 설계도면을 바탕으로 차폐체를 구현한 후 366 keV 이상에 감마선들에 대하여 캡슐용기의 방사선 누설선량을 GEANT4 전사모사를 이용하여 평가하였다. 치료용 I-131 캡슐용기 누설선량을 측정하기 위해 각각의 용기에 대하여 용기 표면에서 10 cm 거리 및 100 cm 거리에서의 누설선량을 측정하였다. 용기표면에서 10 cm 거리와 100 cm 거리에서의 누설선량 측정은 방사형으로 발생되는 방사선을 위치별로 측정하기 위해 $10{\times}10{\times}10cm^3$ 부피의 정육면체 형태의 물 팬텀(phantom)을 상부, 상부측면, 측면, 하부측면, 하부 다섯 방향에 설치하여 누설선량을 계산하였다. 용기별로 5개 방향에서 용기표면으로 부터 10 cm, 100 cm 거리에서 전산모사를 수행한 결과 법적 허용기준인 10 cm 거리에서 2.0 mSv/h, 100 cm 거리에서 0.02 mSv/h 이하의 선량 규정과 비교하였을 때 법적기준치보다 현저히 낮은 누설선량이 방출되는 것을 확인하였다.

• Nuclear Engineering and Technology
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• 제14권4호
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• pp.196-203
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• 1982

본 논문에서는 고리 1호기의 기사용 핵연료 집합체를 수송하기 위한 Cask를 설계하였다. 이를 위하여 고리 1호기의 기사용 핵연료 집합체로부터 방출되는 감마선과 중성자를 계산하여 MORSE 및 ANISN전산 코드로써 차폐 계산을 수행하였다. 그 결과, 9개의 집합체를 동시에 수송할 수 있는 Steel Cask가 가장 적합하다는 것을 밝혔다. 이 Steel Cask에 대한 안전성을 평가하기 위하여 연료봉의 중심 온도와 복재온도를 계산하여 핵연료의 용융점보다 훨씬 낮음을 증명하였다. 또한 KENO와 MORSE전산 코드를 사용하여 임계도 계산을 수행하여 미임계 상태임을 증명하였다. 이로써 9개의 기사용 핵연료 집합체를 동시에 수송할 수 있는 Steel Cask를 간단히 설계하였다.

• 대한방사선기술학회지:방사선기술과학
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• 제44권3호
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• pp.247-252
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• 2021

As the number of single-person households increases, the consumption of bottled water is increasing. In addition, as the public's interest in radioactivity increases, interest in the field of living radioactivity is also increasing. Since drinking water is an essential element in our daily life, it must be safe from radioactivity. In this study, gamma radiation of drinking spring water was measured and internal exposure dose evaluation was performed to determine its harmfulness. K-40 and uranium-based radioactivity analysis was performed through a high-purity germanium detector, and as a result, drinking water was detected somewhat higher than that of mixing water. Since there is no regulation on the natural radioactivity concentration in Korea, it was compared with the U.S. Environmental Protection Agency Drinking Water Regulations and World Health Organization standard. As a result, there were some items that exceeded standards. Internal exposure was evaluated according to the effective dose formula of ICRP 119. As the result was derived that a maximum of 1.17 mSv per year could be received. This result means that the dose limit for the general public may be exceeded, and it was judged that it is necessary to set an appropriate standard value and present a recommendation value through continuous monitoring in the future.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.207-215
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• 2024

This study focuses on measuring the levels of naturally occurring radioactivity in the soil of Swabi, Khyber Pakhtunkhwa, Pakistan, as well as the associated health hazard. Thirty (30) soil samples were collected from various locations and analyzed for ²²⁶Ra, ²³²Th, and ⁴⁰K radioactivity levels using a High Purity Germanium detector (HPGe) gamma-ray spectrometer with a photo-peak efficiency of approximately 52.3%. The average values obtained for these radionuclides are 35.6 ± 5.7 Bqkg^-1, 47 ± 12.5 Bqkg^-1, and 877 ± 153 Bqkg^-1, respectively. The level of ²³²Th is slightly higher and ⁴⁰K is 2.2 times higher than the internationally recommended limit of 30 Bqkg^-1 and 400 Bqkg^-1, respectively. Various parameters were calculated based on the results obtained, including Radium Equivalent (Ra_eq), External Hazard (H_ex), Absorbed Dose Rate (D), Annual Gonadal Equivalent Dose (AGDE), Annual Effective Dose Rate, and Excess Lifetime Cancer Risk (ELCR), which are 170.3 ± 24 Bqkg^-1, 0.46 ± 0.06 Bqkg^-1, 81.4 ± 2.04 nGy h^-1, 582 ± 78.08 µSvy^-1, 99.8 ± 13.5 µSv Gy^-1, and 0.349 ± 0.04, respectively. These values are below the limits recommended by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) in 2002. This study highlights the potential radiation threats associated with natural radioactivity levels in the soil of Swabi and provides valuable information for public health and safety.