• Journal of Radiation Protection and Research
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• 제45권1호
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• pp.16-25
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• 2020

Background: To investigate radiological effects on biota, it is necessary to assess radiation dose for flora and fauna living in a terrestrial ecosystem. This paper presents a dynamic model to assess radioactivity concentration and radiation dose of terrestrial flora and fauna after a nuclear accident. Materials and Methods: Litter, organic soil, mineral soil, trees, wild crops, herbivores, omnivores, and carnivores are considered the major components of a terrestrial ecosystem. The model considers the physicochemical and biological processes of interception, weathering, decomposition of litter, percolation, root uptake, leaching, radioactive decay, and biological loss of animals. The predictive capability of the model was investigated by comparison of its predictions with field data for biota measured in the Fukushima forest area after the Fukushima nuclear accident. Results and Discussion: The predicted radioactive cesium inventories for trees agreed well with those for evergreens and deciduous trees sampled in the Fukushima area. The predicted temporal radioactivity concentrations for animals were within the range of the measured radioactivity concentrations of deer, wild boars, and black bears. The radiation dose for the animals were, for the whole simulation time, estimated to be much smaller than the lower limit (0.1 mGy·d^-1) of the derived consideration reference level given by the International Commission on Radiological Protection for terrestrial flora and fauna. This suggested that the radiation effect of the accident on the biota in the Fukushima forest would be insignificant. Conclusion: The present dynamic model can be used effectively to investigate the radiological risk to terrestrial ecosystems following a nuclear accident.

• 한국방사선학회논문지
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• 제14권5호
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• pp.661-668
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• 2020

임산부의 사망 원인으로 색전증이 발생하며, 이를 검사하기 위해 흉부 방사선 검사를 수행한다. 이외에도 분만 전 응급 수술을 대비하거나 기본 진단 등의 목적으로 검사가 수행된다. 실제 측정을 통해 태아 선량을 평가하는 것은 윤리적 문제가 따르기 때문에, 사전연구로 제작된 팬텀을 통해 흉부 후전방향 검사에서 임신 주 수에 따른 임산부의 장기선량 및 태아선량을 평가하였다. 모의실험 결과 임신 주 수에 따라 태아선량은 감소하였으며, 약 0.1 mGy의 선량을 나타내었다. 차폐를 사용할 때, 차폐 물성으로 밀도가 높고, 두께가 두꺼울수록 차폐 효과가 우수하며 차폐 물성과 두께에 따라 40 ~ 98% 선량이 감소하였다. 또한 완전차폐보다 단면차폐로도 태아선량을 감소하는 것을 확인할 수 있었다. 이후 다양한 차폐물성과 방법 등을 통해 태아선량을 줄일 수 있는 연구가 필요한 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4576-4582
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• 2023

The Korea retrospective dosimetry (KREDOS)-electron paramagnetic resonance (EPR) group undertook an intercomparison investigation utilizing hydroxyapatite. This analysis involved four institutions: the Korea Institute of Radiological and Medical Sciences, Dongnam Institute of Radiological and Medical Sciences, Korean Association for Radiation Application, and Radiation Health Institute of Korea Hydro & Nuclear Power. Following the irradiation of the hydroxyapatite sample, the recorded build-up was analyzed. To validate the reliability of the EPR dosimetry findings and enhance its operational performance, a hydroxyapatite dose-response curve was plotted and dosimetry was performed for a blind sample. The proficiency of each laboratory was assessed by employing an interlaboratory comparison methodology. This involved a comparative analysis of the measurement results by calculating the relative bias, z-score, and En value. The results submitted by the participating laboratories demonstrated satisfactory ratings for doses of 1.006, 3.999, and 6.993 Gy. Following the second intercomparison, efforts to optimize their hydroxyapatite-EPR dosimetry systems are underway in the participating laboratories. The current assessment of hydroxyapatite dose yielded the foundational data required to establish the parameters of dental dosimetry. In future, the third intercomparison experiment will be conducted for exploring other materials.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.231-240
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• 2001

When it is assumed that PWR, CANDU and DUPIC spent fuels are disposed of in deep geological repository, consequent annual individual doses are calculated, and it is shown that doses meet the regulatory limit. From these results, the hazardous radionuclides applicable to partitioning and transmutation are selected. These selected radionuclides such as Tc-99, Ⅰ-129, Cs-135 and Np-237 are then reviewed in terms of partitioning and transmutation. Separation of I-129, Np-237 and Tc-99 from spent fuels is considered desirable, and transmutation of these radionuclides results in remarkable hazard reduction. However, it is concluded that separation and transmutation of Cs-135 may be ineffective although it is classified into a hazardous radionuclide.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1225-1233
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• 2024

Level 3 probabilistic safety assessment (PSA) is performed to calculate radionuclide concentrations and exposure dose resulting from nuclear power plant accidents. To calculate the external exposure dose from the released radioactive materials, the radionuclide concentrations are multiplied by two factors of dose coefficient and a finite cloud dose correction factor (FCDCF), and the obtained values are summed. This indicates that a standard set of FCDCFs is required for external exposure dose calculations. To calculate a standard set of FCDCFs, the effective distance from the release point to the receptor along the wind direction should be predetermined. The TID-24190 document published in 1968 provides equations to calculate FCDCFs and the resultant standard set of FCDCFs. However, it does not provide any explanation on the effective distance required to calculate the standard set of FCDCFs. In 2021, Sandia National Laboratories (SNLs) proposed a method to predetermine finite effective distances depending on the atmospheric stability classes A to F, which results in six standard sets of FCDCFs. Meanwhile, independently of the SNLs, the authors of this paper discovered that an infinite effective distance assumption is a very reasonable approach to calculate one standard set of FCDCFs, and they implemented it into the multi-unit radiological consequence calculator (MURCC) code, which is a post-processor of the level 3 PSA codes. This paper calculates and compares short- and long-range FCDCFs calculated using the TID-24190, SNLs method, and MURCC method, and explains the strength of the MURCC method over the SNLs method. Although six standard sets of FCDCFs are required by the SNLs method, one standard sets of FCDCFs are sufficient by the MURCC method. Additionally, the use of the MURCC method and its resultant FCDCFs for level 3 PSA was strongly recommended.

• 한국방사선학회논문지
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• 제12권2호
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• pp.209-216
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• 2018

혈관조영 및 중재적 방사선학 분야의 경우, 업무 특성상 눈의 방사선 피폭에 대한 위험성이 높다고 알려져 있으나, 현재 구분된 선량평가 및 관리가 이루어지지 않는 실정이다. 이에 본 연구에서는 시술 환경 내 종사자의 눈에 대한 선량평가 및 차폐분석을 위해 첫 번째로, 시술자가 주로 위치하는 지점을 선정하고, 두경부 팬텀 눈의 외안각 지점에 포켓선량계를 부착한 뒤 눈에 대한 피폭선량을 평가하였고, 현재 상용화된 납 안경 착용 시 차폐효과를 산정하였다. 두 번째로, 실측과 동일한 기하학적 구조 내 모의실험을 통해 눈의 피폭선량에 대한 경향성 평가와 차폐효과에 대해 분석하였다. 그 결과, 선량계를 이용한 측정의 경우, 방사선 투시촬영 시간이 증가함에 따라 누적선량이 증가하였고, 또한 시술자의 위치에 따라 각기 다른 양상을 보였다. 모의실험의 경우, 수학적 팬텀 내 눈의 수정체의 경우 각막보다 약 1.1 ~ 1.3배 높은 선량분포를 나타내는 것을 확인하였고, 납 안경의 방호효과는 눈의 각 기관별로 최소 3.7 ~ 최대 21.4% 차폐효과를 보였다.

• 한국방사선학회논문지
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• 제11권7호
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• pp.555-564
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• 2017

직업상 피폭에 대한 현행 방사선 위험성 평가는 종사자의 피폭선량 평가 및 건강진단에 중점을 두고 있다. 이러한 개인 중심의 위험성 평가는 선량계 미착용 및 개개인의 기호로 인한 건강영향 문제 등 정확한 데이터 확보의 어려움으로 인한 오류의 가능성이 있다. 또한 평가의 기준이 되는 선량한도는 법적 최대 상한값으로 방사선 방호에 최적화된 값을 의미하지는 않는다. 이에 선원적, 환경적 및 인적 측면을 복합적으로 고려할 수 있고 방사선방호의 최적화를 이행할 수 있는 국가적 차원의 새로운 위험성 평가 모델이 요구되고 있다. 본 연구에서는 고용노동부의 위험성 평가에 기반하여 개인이 아닌 작업장 중심의 위험성 평가 모델을 연구하였다. 이를 위해 여러 분야의 위험성 추정 방법을 분석하여 방사선 분야에 적용하기 적합한 모델을 도출하고, 모델에 적용하기 위한 데이터 획득 방법 및 절차에 대해 기술하였다. 본 연구에서 도출한 작업장 중심의 다차원적 위험성 평가 모델은 위험성을 점수화하고 Rader Plot을 이용하여 표현함으로서 보다 정확한 방사선 위험성 평가를 가능하게 하며, 결론적으로 효율적인 종사자 관리, 선제적 종사자 보호 및 방사선 방호의 최적화 이행에 기여할 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2239-2246
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• 2024

The present study aimed to assess the radioactive hazards associated with the application of granitoid rocks in building materials. An HPGe spectrometer was used to detect the levels of the radioactive elements uranium-238, thorium-232, and potassium-40 in the granitoid rocks. The results showed that the levels of these elements were lower (38.32 < 33 Bq kg^-1), comparable (47.19-45 Bq kg^-1) and higher (992.26 ≫> 412 Bq kg^-1) than the worldwide limits for ²³⁸U, ²³²Th, and ⁴⁰K concentration, respectively. The exposure to gamma radiation of granitoid rocks was studied by various radiological hazard variables like the absorbed dose rate (D_air), the outdoor and indoor annual effective dose (AED_out and AED_in), and excess lifetime cancer risk (ELCR). A variety of statistical methods, including Pearson correlation, principal component analysis (PCA), and hierarchical cluster analysis (HCA) was used, to study the relationship between the radioactive elements and the radiological hazards. According to statistical analysis, the main radioactive risk of granitoid rocks is contributed to by the elements uranium-238, thorium-232, and potassium-40. Granitoid rocks can be applied in building materials, but under control to prevent risk to the public.

• Nuclear Engineering and Technology
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• 제42권1호
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• pp.1-8
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• 2010

Geological disposal is designed to provide safe containment of radioactive waste for very long times, with the containment provided by a combination of engineered and geological barriers. In the extreme long term, after many thousands of years or longer, residual amounts of long-lived radionulides such as Cl-36, but also radionuclides in the natural decay chains, may be released into the environment normally accessed and used by humans, termed here, the biosphere. It is necessary to ensure that any such releases meet radiation protection objectives through the development of a safety case, which will include assessment of radiation doses to humans. The design of such dose calculations over such long timeframes is not straightforward, because of the range of potentially relevant assumptions which could be made, concerning environmental change and changes in human behavior. These conceptual uncertainties are additional to those that more typically arise, for example, in the assessment of present day situations, but which also have to be addressed. The issue has therefore been subject to international cooperation for many years. This paper summarizes the evolution and results of that collaboration leading up to the present day, taking account of developments in international recommendations on radiation protection objectives and the more recent greater focus on preparation of site specific safety cases.

• Nuclear Engineering and Technology
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• 제52권10호
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• pp.2379-2386
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• 2020

This paper presents the results of the first intercomparison exercise performed by the Korea retrospective dosimetry (KREDOS) working group using electron paramagnetic resonance (EPR) spectroscopy. The intercomparison employed the alanine dosimeter, which is commonly used as the standard dosimeter in EPR methods. Four laboratories participated in the dose assessment of blind samples, and one laboratory carried out irradiation of blind samples. Two types of alanine dosimeters (Bruker and Magnettech) with different geometries were used. Both dosimeters were blindly irradiated at three dose levels (0.60, 2.70, and 8.00 Gy) and four samples per dose were distributed to the participating laboratories. Assessments of blind doses by the laboratories were performed using their own measurement protocols. One laboratory did not participate in the measurements of Magnettech alanine dosimeter samples. Intercomparison results were analyzed by calculating the relative bias, E_n value, and z-score. The results reported by participating laboratories were overall satisfactory for doses of 2.70 and 8.00 Gy but were considerably overestimated with a relative bias range of 10-95% for 0.60 Gy, which is lower than the minimum detectable dose (MDD) of the alanine dosimeter. After the first intercomparison, participating laboratories are working to improve their alanine-EPR dosimetry systems through continuous meetings and are preparing a second intercomparison exercise for other materials.