• Nuclear Engineering and Technology
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• 제23권4호
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• pp.387-400
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• 1991

해수유동에 의한 이류와 부유물과의 상호작용에 의한 해양에서의 핵종이동을 모사하여 시간에 따른 핵종농도의 파과곡선을 구할 수 있는 해양구획모델이 개발되었다. 해양을 임의 수의 구획으로 나누어 각 구획간의 질량수지를 통해 지배 방정식을 세우고 이에 대한 해를 stiff한 문제에 유용한 수치적분방법을 이용하여 구하였다. 2차원 해수유동모델을 이용하여 해수교체시간을 계산한 후 각 구획간의 해수유동에 의한 이류수송을 나타내는 이동계수를 구하였다. 개발된 해양구획모델에 대한 계산 예로써 해저에 위치한 가상 처분장으로 부터 방출된 저준위방사성 폐기물의 주요 핵종중 Tc-99 Cs-137 및 Pu-238에 대한 파과곡선을 5개 구획에 대해 구하였다. 또한 핵종농도 파가 곡선에 대한 파라미터의 민감도 분석을 수행한 결과 구획내의 해수체적 및 해수교체시간과 같은 주요 변수들이 파과곡선에 중요한 영향을 줌을 알 수 있었다.

• 한국환경과학회지
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• 제24권3호
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• pp.275-280
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• 2015

In order to measure the Radionuclides and Concentration, the directly grinded land samples (river soil, pine leaves and mugwort) among the environment samples around the nuclear power plant were filled in a 450 mL Marinelli beaker and weighed to obtain the dry mass ratio of the samples. Then the background and land samples were measured for 80,000 sec. The analysis of the collected land samples showed that most of them contained less radiation nuclide than the detection minimum limit in the 'Ministry of Education, Science and Technology Public Notice No. 2010-32.'In others, the natural radionuclides $^{40}K$ were detected. Of the products of nuclear reaction discharged by a nuclear reaction, $^{134}Cs$ and $^{137}Cs$ are more easily detected, and their discharge sources can be traced using the relative ratio. Although the radioactive concentration in the vicinity of Kori Nuclear Power Plant, which is more than 1,100km away from Fukushima, the Japanese nuclear accident site, continuous monitoring is needed as the radionuclides can still be accumulated in the soil or animals and plants.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.52-57
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• 2004

해체부지 선량평가 모델의 주요 핵종에 대한 key parameter를 분석하기 위하여 민감도 분석을 수행하였다. 본 연구에서 민감도 분석을 수행하기 위한 주요 가정 사항으로서 피폭시나리오는 가장 보수적인 resident farmer를 그리고 방사성핵종의 오염 정도는 0.037 Bq/g로 하였다. 분석결과, 감마 방출 핵종인 Cs-137과 Co-60의 경우에는 오염지역의 면적과 거주관련 변수(외부감마차폐인자와 실내 거주시간분율), C-14 핵종의 경우에는 환경변수와 불포화층의 수문학적 변수가, Sr-90 핵종의 경우에는 오염지역의 토양 밀도가 선량에 미치는 영향이 큰 parameter로 확인되었다.

• Nuclear Engineering and Technology
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• 제56권7호
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• pp.2452-2457
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• 2024

To obtain site-specific values of the Derived Concentration Guideline Levels (DCGLs) for decommissioning of KRR-1&2, the soil density and distribution coefficient values for Cs-137, a major contaminant radionuclide, were determined. The soil density was evaluated according to the test method established by the Korean Agency for Technology and Standards of the Ministry of Trade, Industry, and Energy (KATS). The distribution coefficient was evaluated using a batch test. The validity of using the evaluated soil density and distribution coefficient as site-specific values was assessed through radiation dose assessment reflecting these values. Average soil density value obtained was 1.738 g/cm³, which was within the typical range of normal soil density, 1.0-1.8 g/cm³. The average distribution coefficient value was 7,754 mL/g. Applying the maximum, average, and minimum values of the evaluated soil density and distribution coefficient showed similar radiation dose results, thus suggesting that it is reasonable to use the average values of each parameter as site-specific values. Findings of this study can help determine DCGLs that reflect the characteristics of the research reactor site.

• 방사성폐기물학회지
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• 제5권3호
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• pp.179-188
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• 2007

가압경수로형 원자력발전소의 운영과정에서 발생된 폐수지내 $^{14}C$ 및 $^3H$의 분포특성을 조사하였다. $Na_2^{14}CO_3$ 표준용액을 사용한 $^{14}C$의 회수율 측정결과, 사용한 산의 종류에 관계없이, 3 N-HCl $3\;N-HNO_3,\;3\;N-H_2SO_4$, 주입한 $^{14}C$ 농도 $0.72\;Bq{\sim}460\;Bq$ 범위에서 $81%{\sim}100%$의 회수율을 나타내었다. 같은 장치를 사용하여 HTO 표준용액 증류에 의한 $^3H$의 회수율은 주입한 $^3H$ 농도 $0.60\;Bq{\sim}435\;Bq$ 범위에서 $81%{\sim}101%$ 이었다. 습식산화-산용출법에 의한 폐수지의 $^{14}C$ 및 $^3H$ 동시분리시, $3\;N-H_2SO_4$를 사용했을 때 다른 감마핵종에 의한 방해가 없었으며, $^3H$ 포집액이 섬광제와 잘 혼합되었다. 그러나 3 N-HCl을 사용했을 때 $^3H$ 포집용액에서 $^{60}Co,\;^{134}Cs,\;^{137}Cs$ 및 $^{54}Mn$ 등의 감마핵종이 검출되었다. 또한 Sample Oxidizer에 의한 $^3H$ 포집용액에서도 $^{60}Co,\;^{134}Cs,\;^{137}Cs$ 및 $^{54}Mn$ 등이 검출되었으며, $^{14}C$ 포집용액에서는 $^{134}Cs,\;^{137}Cs$이 검출되었다. 폐수지의 총 $^{14}C$ 함량중 약 70% 이상이 무기 탄소로 확인되었다. 30개 폐수지 시료중 8개 고방사능 폐수지의 $^{14}C$ 및 $^3H$의 평균농도는 각각 $19000\;Bq/g{\pm}41000\;Bq/g,\;670\;Bq/g{\pm}460\;Bq/g$이었으며 22개 저방사능폐수지에서는 각각 $4.2\;Bq/g{\pm}4.3\;Bq/g,\;6.0\;Bq/g{\pm}5.3\;Bq/g$이 검출되었다. 고방사능 폐수지의 평균 $^{14}C/^3H$비는 28로 저방사능 폐수지의 0.70에 비해 높게 나타났으며, $^{14}C$ 및 $^3H$의 농도는 서로 비례하는 경향을 보였다.

• Membrane and Water Treatment
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• 제9권5호
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• pp.327-334
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• 2018

The nano/micro composites with highly porous surface area have attracted of great interest, particularly the synthesis of porous and thin film sheets of high performance. In this paper, an easy method of cost-effective synthesis of thin film ceramic fiber membranes based on Hydroxyapatite, and activated carbon by turned into studied to be applied within the service-facilitated the transport of radioactive waste such as $^{90}Sr$, $^{137}Cs$ and $^{60}Co$) as activated product of radioisotopes from ETRR-2 research reactor and dissolved in 3M $HNO_3$, across a thin flat-sheet supported liquid membrane (TFSSLM). Radionuclides are transported from alkaline pH values. The presence of sodium salts in the aqueous media improves in $HNO_3$, the lowering of permeability because the initial $HNO_3$ concentration is improved. The study some parameters on the thin sheet ceramic supported liquid membrane. EDTA as stripping phase concentration, time of extraction and temperature were studied. The study of maximum permeability of radioisotopes for all parameters. The pertraction of a radioactive waste solution from nitrate medium were examined at the optimized conditions. Under the optimum experimental 98.6-99.9% of $^{90}Sr$, 79.65-80.3% of $^{137}Cs$ and $^{60}Co$ 45.5-55.5% in 90-110 min with were extracted in 10-30 min, respectively. The process of diffusion in liquid membranes is governed by the chemical diffusion process.

• 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.

• 동위원소회보
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• 제21권4호
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• pp.55-65
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• 2006

A passive type radon monitor adopting two silicon PIN detector as radiation detector has been developed, manufactured and test-evaluated. A radiation signal processing circuit has been electronically tested and then the radiation detection characteristics of this instrument has been performance-tested by using reference radon concentration and a reference photon radiation field. As a result, in a electronic performance test, radiation signals from each detector were well observed in each signal processing circuit. The radiation detection sensitivity of this instrument after several test-irradiations to a Cs-137 gamma radiation source and a standard radon concentration appeared to be 1.37 cph/$\mu$Svh-1 and 1.66 pCi/L respectively. The developed radon monitor in this paper could be used conveniently in monitoring of radon concentration in buildings which population utilize in Korea.

• Nuclear Engineering and Technology
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• 제35권5호
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• pp.387-398
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• 2003

For reference human intrusion scenarios constructed in previous study, a probabilistic safety assessment to derive the radionuclide concentration limits for the low- and intermediate- level radioactive waste disposal facility is conducted. Statistical approach by the Latin Hypercube Sampling method is introduced and new assumptions about the disposal facility system are examined and discussed. In our previous study of deterministic approach, the post construction scenarios appeared as most limiting scenario to derive the radionuclide concentration limits. Whereas, in this statistical approach, the post drilling and the post construction scenarios are mutually competing for the scenario selection according to which radionuclides are more important in safety assessment context. Introduction of new assumption shows that the post drilling scenario can play an important role as the limiting scenario instead of the post-construction scenario. When we compare the concentration limits between the previous and this study, concentrations of radionuclides such as Nb-94, Cs-137 and alpha-emitting radionuclides show elevated values than the case of the previous study. Remaining radionuclides such as Sr-90, Tc-99 I-129, Ni-59 and Ni-63 show lower values than the case of the previous study.

• Journal of Radiation Protection and Research
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• 제45권3호
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• pp.101-107
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• 2020

Background: An important lesson learned from the Fukushima accident is that the transition to the mid- and long-term phases from the emergency-response phase requires less than a year, which is not very long. It is necessary to know how much radioactive material has been deposited in an urban area to establish mid- and long-term countermeasures after a radioactive accident. Therefore, an urban deposition model that can indicate the site-specific characteristics must be developed. Materials and Methods: In this study, the generalized urban deposition velocity and the subsequent variation in radionuclide contamination were estimated based on the characteristics of the Korean urban environment. Furthermore, the application of the obtained generalized deposition velocity in a hypothetical scenario was investigated. Results and Discussion: The generalized deposition velocities of ¹³⁷Cs, ¹⁰⁶Ru, and ¹³¹I for each residence type were obtained using three-dimensional (3D) modeling. For all residence types, the deposition velocities of ¹³¹I are greater than those of ¹⁰⁶Ru and ¹³⁷Cs. In addition, we calculated the generalized deposition velocities for each residential types. Iodine was the most deposited nuclide during initial deposition. However, the concentration of iodine in urban environment drastically decreases owing to its relatively shorter half-life than ¹⁰⁶Ru and ¹³⁷Cs. Furthermore, the amount of radioactive material deposited in nonresidential areas, especially in parks and schools, is more than that deposited in residential areas. Conclusion: In this study, the generalized urban deposition velocities and the subsequent deposition changes were estimated for the Korean urban environment. The 3D modeling was performed for each type of urban residential area, and the average deposition velocity was obtained and applied to a hypothetical accident. Based on the estimated deposition velocities, the decision-making systems can be improved for responding to radioactive contamination in urban areas. Furthermore, this study can be useful to predict the radiological dose in case of large-scale urban contamination and can support decision-making for long-term measurement after nuclear accident.