• Journal of Radiation Protection and Research
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• 제48권2호
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• pp.84-89
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• 2023

Background: Food consumption is one of the most important routes for radionuclide intake for the public; therefore, there is the need to have a comprehensive understanding of the amount of radioactivity in food products. Consumption of radionuclide-contaminated food could increase potential health risks associated with exposure to radiation such as cancers. The present study aims to determine radioactivity levels in some food products (milk, rice, sugar, and wheat flour) consumed in Mali and to evaluate the radiological effect on the public health from these radionuclides. Materials and Methods: The health impact due to ingestion of radionuclides from these foods was evaluated by the determination of activity concentration of radionuclides ²³⁸U, ²³²Th, ⁴⁰K, and ¹³⁷Cs using gamma spectrometry system with high-purity germanium detector and radiological hazards index in 16 samples collected in some markets, mall, and shops of Bamako-Mali. Results and Discussion: The average activity concentrations were 9.8±0.6 Bq/kg for ²³⁸U, 8.7±0.5 Bq/kg for ²³²Th, 162.9±7.9 Bq/kg for ⁴⁰K, and 0.0035±0.0005 Bq/kg for ¹³⁷Cs. The mean values of radiological hazard parameters such as annual committed effective dose, internal hazard index, and risk assessment from this work were within the dose criteria limits given by international organizations (International Commission on Radiological Protection and United Nations Scientific Committee on the Effects of Atomic Radiation) and national standards. Conclusion: The results show low public exposure to radioactivity and associated radiological impact on public health. Nevertheless, this study stipulates vital data for future research and regulatory authorities in Mali.

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1505-1512
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• 2017

Because accelerator-based boron neutron capture therapy (BNCT) systems are planned for use in hospitals, entry into the medical room should be controlled as hospitals are generally assumed to be public and safe places. In this paper, computational investigation of the medical staff effective dose during BNCT has been performed in different situations using Monte Carlo N-Particle (MCNP4C) code and two voxel based male phantoms. The results show that the medical staff effective dose is highly dependent on the position of the medical staff. The results also show that the maximum medical staff effective dose in an emergency situation in the presence of a patient is ${\sim}25.5{\mu}Sv/s$.

• 방사성폐기물학회지
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• 제21권2호
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• pp.183-191
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• 2023

The potential impact of hypothetical accidents that occur during the immediate and deferred dismantling of the Kori Unit 1 steam generator has been comprehensively evaluated. The evaluation includes determining the inventory of radionuclides in the Steam Generator based on surface contamination measurements, assuming a rate of release for each accident scenario, and applying external and internal exposure dose coefficients to assess the effects of radionuclides on human health. The evaluation also includes calculating the atmospheric dispersion factor using the PAVAN code and analyzing three years of meteorological data from Kori NPP to determine the degree of diffusion of radionuclides in the atmosphere. Overall, the effective dose for residents living in the Exclusion Area Boundary (EAB) of Kori NPP is predicted, an it is found that the maximum level of the dose is 0.034% compared to the annual dose limit of 1 mSv for the general public. This implies that the potential impact of hypothetical accidents on human health discussed above is within acceptable limits.

• 한국독성학회:학술대회논문집
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• 한국독성학회 2001년도 International Symposium on Dietary and Medicinal Antimutgens and Anticarcinogens
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• pp.178-178
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• 2001

The interaction of extremely low frequency magnetic field (ELF-MF) on the frequency of micronuclei (MN) induced by benzo(a)pyrene (BP) in human lymphocytes was examined. A 60 Hz ELF-MF of 0.8 mT field strength was applied for 24 hours either alone or with the tumour initiator, BP. The frequency of MN induced by BP increased in a dose-dependent manner.(omitted)

• 한국산학기술학회논문지
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• 제11권6호
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• pp.2118-2123
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• 2010

국내의 경우 방사선작업종사자의 개인피폭관리는 선량한도를 초과한 피폭의 유무를 확인하여 사후 조치를 취하는 것에 초점이 맞추어져 있다. 그러나 의료기관 핵의학과의 경우 개봉선원을 사용하므로 작업환경이 방사선에 노출될 가능성이 많고, 방사성의약품 투여 후 수 시간 혹은 수 일 동안은 환자 자체가 방사선원이 되므로 방사선작업종사자나 수시출입자, 환자보호자들의 방사선 피폭 가능성이 매우 높다. 따라서 환자보호자 등 일반출입자의 방사선피폭을 방지하기 위해서는 환경방사선관리가 적절하게 실시되어야 한다. 일본에서는 "방사성동위원소등에 의한 방사선장해의 방지에 관한 법률" 등에 근거하여 방사선작업환경에 대한 환경방사선량을 정기적으로 측정, 보관하도록 하고 있다. 이에 대전시 소재 대학병원 핵의학과에서 일본에서 시행하고 있는 것과 같은 방법으로 핵의학과 내 8개소에 유리선량계를 설치하여 환경방사선을 측정한 결과 8개소 모두 "진단용 방사선 발생장치의 안전관리에 관한 규칙"에 규정된 방사선구역의 외부방사선량인 주당 0.3 mSv에는 훨씬 미치지 못하는 적은 선량이 측정되었다. 그러나 접수대에서는 3개월 누계 선량률이 0.51 mSv로서 접수대 종사자는 일반인 연간 유효선량한도인 1 mSv를 초과할 가능성이 높았으며, 환자 및 보호자 대기실에서도 0.23 mSv(3개월 누계치 0.69mSv)가 측정되어 유리선량계를 설치한 8개소 가운데 가장 높은 선량률을 보였다. 이것은 일반인의 연간 유효선량한도인 1 mSv를 초과하는 값이며, "방사선방호 등에 관한 기준 고시"에 환경상 위해방지를 위해 규정된 연간 유효선량 0.25 mSv를 초과하는 값이다. 따라서 접수대 근무자, 환자보호자 및 제3자 보호를 위해 핵의학과 내 환경방사선량 감소를 위한 적극적인 대책이 필요한 것으로 나타났다.

• Nuclear Engineering and Technology
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• 제52권6호
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• pp.1231-1242
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• 2020

The Kori Unit 1 will be decommissioned after a permanent shutdown in June 2017. South Korea has a 0.1 mSv/yr exposure limit standard for limited or unlimited site release. This is South Korea's first commercial NPP; therefore, if the containment building is reused as a memorial hall, it will contribute to the improvement of public understanding and enhance the public's acceptance of NPPs. Also, existing Kori Unit 1 nuclear power plant manpower resources can be reused after decommissioning and resident staff and memorial hall visitors can activate nearby commercial areas. Therefore, such a reuse scenario may also prevent an economic recession. The exposure dose was calculated using the following scenarios: worker in the containment building, visitor in the containment building, and worker in buildings other than the containment building. The exposure dose in the buildings was calculated by the RESRAD-BUILD developed by the Argonne National Laboratory (ANL). The preliminary exposure dose and derived concentration guideline level (DCGL) were derived.

• Communications for Statistical Applications and Methods
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• 제29권4호
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• pp.421-439
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• 2022

Phase I dose-finding trials are essential in drug development. By finding the maximum tolerated dose (MTD) of a new drug or treatment, a Phase I trial establishes the recommended doses for later-phase testing. The primary toxicity endpoint of interest is often a binary variable, which describes an event of a patient who experiences dose-limiting toxicity. However, there is a growing interest in dose-finding studies regarding non-binary outcomes, defined by either the weighted sum of rates of various toxicity grades or a continuous outcome. Although several novel methods have been proposed in the literature, accessible software is still lacking to implement these methods. This study introduces a newly developed R package, UnifiedDoseFinding, which implements three phase I dose-finding methods with non-binary outcomes (Quasi- and Robust Quasi-CRM designs by Yuan et al. (2007) and Pan et al. (2014), gBOIN design by Mu et al. (2019), and by a method by Ivanova and Kim (2009)). For each of the methods, UnifiedDoseFinding provides corresponding functions that begin with next that determines the dose for the next cohort of patients, select, which selects the MTD defined by the non-binary toxicity endpoint when the trial is completed, and get oc, which obtains the operating characteristics. Three real examples are provided to help practitioners use these methods. The R package UnifiedDoseFinding, which is accessible in R CRAN, provides a user-friendly tool to facilitate the implementation of innovative dose-finding studies with nonbinary outcomes.

• Journal of Radiation Protection and Research
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• 제47권2호
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• pp.77-85
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• 2022

Background: After the Fukushima Daiichi Nuclear Power Station (FDNPS) accident, a model was developed to estimate the external exposure doses for residents who were expected to return to their homes after evacuation orders were lifted. However, the model's accuracy and uncertainties in parameters used to estimate external doses have not been evaluated. Materials and Methods: The model estimates effective doses based on the integrated ambient dose equivalent (H^*(10)) and life patterns, considering a dose reduction factor to estimate the indoor H^*(10) and a conversion factor from H^*(10) to the effective dose. Because personal dose equivalent (H_p(10)) has been reported to agree well with the effective dose after the FDNPS accident, this study validates the model's accuracy by comparing the estimated effective doses with H_p(10). The H_p(10) and life pattern data were collected for 36 adult participants who lived or worked near the FDNPS in 2019. Results and Discussion: The estimated effective doses correlated significantly with H_p(10); however, the estimated effective doses were lower than H_p(10) for indoor sites. A comparison with the measured indoor H^*(10) showed that the estimated indoor H^*(10) was not underestimated. However, the H_p(10) to H^*(10) ratio indoors, which corresponds to the practical conversion factor from H^*(10) to the effective dose, was significantly larger than the same ratio outdoors, meaning that the conversion factor of 0.6 is not appropriate for indoors due to the changes in irradiation geometry and gamma spectra. This could have led to a lower effective dose than H_p(10). Conclusion: The estimated effective doses correlated significantly with H_p(10), demonstrating the model's applicability for effective dose estimation. However, the lower value of the effective dose indoors could be because the conversion factor did not reflect the actual environment.

• Environmental Analysis Health and Toxicology
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• 제25권1호
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• pp.69-77
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• 2010

The purpose of this study is to evaluate the effectiveness of Scirpi rhizoma ethanol extract (SREE) on skin whitening using in vitro test. In the antioxidative activities, it was found that SREE contains 38.9 mg/g of polyphenol and 74.5 mg/g of flavonoid in total. In the electron donating ability, SREE showed a dose-dependent response, showing a high antioxidative capacity of 86.1% at 1000 ppm. It was found that the maximum permissible level of SREE to Melan-a cells was over 200 ppm, showing a quite low toxicity of SREE against Melan-a cells. Both in the inhibitory measurement for tyrosinase activity and melanogenesis using Melan-a cells, SREE presented a dose-dependent response with excellent efficacy.

• Journal of Radiation Protection and Research
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• 제28권3호
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• pp.247-254
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• 2003

To prevent the potential health detriment to the public from radioactive effluents, radiological dose assessments due to the operation of nuclear facilities located at Korea Atomic Energy Research Institute (KAERI) site has been performed semiannually in compliance with the Minister of Science and Technology (MOST)'s Notice in Korea. Radiological dose assessment based on the new recommendation of the International Committee on Radiation Protection (ICRP-60) has been conducted since 1998. In this manuscript, a serial activities at KAERI site to meet the regulatory standards for routine releases of radioactive effluents are introduced and discussed including technical approaches. It is clear that each nuclear facility has been operated in compliance with regulatory standards. Furthermore, it is identified that the radiation induced health effects for residents around the site are neglectable.