• Nuclear Engineering and Technology
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• 제46권4호
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• pp.547-556
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• 2014

Korea expects a shortage in storage capacity for spent fuels at reactor sites. Therefore, a need for more metal and/or concrete casks for storage systems is anticipated for either the reactor site or away from the reactor for interim storage. For the purpose of interim storage and transportation, a dual purpose metal cask that can load 21 spent fuel assemblies is being developed by Korea Radioactive Waste Management Corporation (KRMC) in Korea. At first the gamma and neutron flux for the design basis fuel were determined assuming in-core environment (the temperature, pressure, etc. of the moderator, boron, cladding, $UO_2$ pellets) in which the design basis fuel is loaded, as input data. The evaluation simulated burnup up to 45,000 MWD/MTU and decay during ten years of cooling using the SAS2H/OGIGEN-S module of the SCALE5.1 system. The results from the source term evaluation were used as input data for the final shielding evaluation utilizing the MCNP Code, which yielded the effective dose rate. The design of the cask is based on the safety requirements for normal storage conditions under 10 CFR Part 72. A radiation shielding analysis of the metal storage cask optimized for loading 21 design basis fuels was performed for two cases; one for a single cask and the other for a $2{\times}10$ cask array. For the single cask, dose rates at the external surface of the metal cask, 1m and 2m away from the cask surface, were evaluated. For the $2{\times}10$ cask array, dose rates at the center point of the array and at the center of the casks' height were evaluated. The results of the shielding analysis for the single cask show that dose rates were considerably higher at the lower side (from the bottom of the cask to the bottom of the neutron shielding) of the cask, at over 2mSv/hr at the external surface of the cask. However, this is not considered to be a significant issue since additional shielding will be installed at the storage facility. The shielding analysis results for the $2{\times}10$ cask array showed exponential decrease with distance off the sources. The controlled area boundary was calculated to be approximately 280m from the array, with a dose rate of 25mrem/yr. Actual dose rates within the controlled area boundary will be lower than 25mrem/yr, due to the decay of radioactivity of spent fuel in storage.

• 자원환경지질
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• 제30권6호
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• pp.587-601
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• 1997

This study had three purposes: (1) to investigate the enrichment levels and dispersion patterns of potentially toxic elements in the rock-soil-plant system; (2) to evaluate the uptake ratios of heavy metals from soils into plants and (3) to assess the chemical speciation of heavy metals in soils. Rock, surface soil and plant samples were collected in the Boeun area underlain by black shales of the Okchon Zone. These samples were analyzed for multi-elements using INAA, ICP-AES and AAS. The maximum abundance of U in black shales is 16 mg/kg and radioactivity counts up to 300 cpm. In particular, Mo, V, Ba, Cd, Pb and U are enriched in black shales. Most of soils derived from black shales show high concentrations of U, As, Mo, Ba, Cu, Cd, Pb, Zn and mean concentrations of As and Mo in soils (20 mg/kg of As and 6.6 mg/kg of Mo) are higher than the permissible level suggested by Kloke (1979). Enrichment index values of soils are calculated and higher than 1.0 in the black shale area with the highest value of 6.4. Mean concentration of Cd in plants is higher than those of Cu, Pb and Zn. The concentration of Cd in plant species decreases in the order of Chinese cabbage > red pepper > soybean=sesame > rice stalk > com > rice grain. The biological absorption coefficients (BAC) in plants are in the order of Cd > Zn=Cu > Pb, which suggests that Cd is more bioavailable to plants than Cu, Pb and Zn. From the results of sequential extraction analysis of soils, relatively high proportion of Cu, Pb and Zn are present as residual fractions whereas that of Cd as non-residual fractions. Cadmuim occurs predominantly as exchangeable/water-acid soluble phase in soils, and Cd is more mobile and bioavailable than Cu, Pb and Zn.

• 방사성폐기물학회지
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• 제3권3호
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• pp.231-236
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• 2005

원전에서 발생하는 건조폐수지를 함유한 고건전성용기(HIC, high integrity container)를 운반하기 위한 HIC 운반용기는 내용물의 높은 방사능으로 인하여 원자력법 및 IAEA의 안전수송규정의 B형 운반용기의 요건을 따라야 하고 정상운반 및 운반사고조건에 대하여 구조적 건전성을 유지하여야 한다. 운반용기는 최대손상을 야기하는 위치에서 단단한 바닥면 위로 9 m 높이에서의 자유낙하충격 및 연강봉 위로의 1 m 높이에서의 낙하충격을 견디어야 한다. HIC 운반용기의 개념설계를 위하여 9 m 자유낙하 및 1 m 파열조건에 대하여 ABAQUS 전산코드를 이용한 3차원동적 구조해석을 수행하고 건전성을 평가하였다.

• Nuclear Engineering and Technology
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• 제24권1호
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• pp.52-62
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• 1992

국내 원자력 발전소의 주요 기종인 가압 경수로에서는 일차 냉각계통을 통한 부식생성물 (CRUD)의 이동에 의해 노심에서 방사화된 후 노외표면에 침적된 방사성 핵종은 원전 종사자 방사선 피폭의 주원인이 된다. 따라서, 부식생성물에 의한 방사선 피폭을 감소시키기 위한 최적 화학운전 방안이 요망된다. 본 연구에서는 운전중인 국내 4개 발전소의 실제 수화학 운전 자료를 분석하였으며, 냉각재 화학운전 자료를 평가하기 위해 냉각재 수화학 조건에 따라 방사능 생성양을 계산할 수 있는 Computer 코드를 이용하였다. 실제 수화학 운전조건과 가정된 Elevated Li 운전조건에 따른 운전결과를 Computer 코드에 의해 예측하여 비교한 결과, Elevated Li 수화학 운전방법을 적용할 경우, 현재 적용되는 수화학 운전방법에 비하여 노심에서 부식생성물의 침적을 감소시킴으로써 노외 방사능 양을 상당히 감소시킬 수 있음을 알았다. 또한 계통 구성재 질과 핵연료봉의 건전성이 보장되는 한 냉각재 pH를 상승시키면 노외 방사능 생성감소에 유리함을 밝혔다.

• 한국의학물리학회지:의학물리
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• 제19권1호
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• pp.1-8
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• 2008

테크니슘$(^{99m}Tc)$은 현재 핵의학 분야에서 진단용 방사선원으로 가장 널리 쓰이고 있는 방사성 동위원소 중 하나이다. 일반적으로 테크니슘은 $^{99m}Tc$ Generator라 불리는 장치 안에서 모핵종인 $^{99}Mo$의 붕괴를 통해 생산되는데, $^{99}Mo$과 $^{99m}Tc$에서 비교적 높은 방사선을 방출하기 때문에 이를 차폐하기 위하여 주로 납으로 제작되어 있다. 본 논문에서는 국내에서 비교적 사용 빈도가 높고 교정 방사능이 500 mCi인 일본 제품을 대상으로, 최대 방사능량 적제조건에서 차폐용기 표면으로부터 10 cm, 100 cm에서 각각 2.0 mSv/h, 0.02 mSv/h를 초과하지 않아야 한다는 국내 법적 제한치를 만족시키는지 여부를 GEANT4를 이용하여 시뮬레이션하였다. 계산 결과 용기 밖으로 방출되는 방사선량이 법적 기준치를 초과하지 않는 것으로 나타났다.

• 한국환경과학회:학술대회논문집
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• 한국환경과학회 2003년도 International Symposium on Clean Environment
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• pp.232-235
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• 2003

In general, the parameters of climate change include aerosol chemical compounds, aerosol optical depth, greenhouse gases(carbon dioxide, CFCs, methane, nitrous oxide, tropospheric ozone), ozone distribution, precipitation acidity and chemical compounds, persistent organic pollutants and heavy metals, radioactivity, solar radiation including ultra-violet and standard meteorological parameters. Over the last ten years, the monitoring activities of Korea regarding to the climate change have been progressed within the WMO GAW and ACE-Asia IOP programs centered at the observation sites of Anmyeon and Jeju Gosan islands respectively. The Greenhouse gases were pointed out that standard air quality monitoring techniques are required to enhance data comparability and that data presentation formats need to be harmonized and easily understood. Especially, the impact of atmospheric aerosols on climate depends on their optical properties, which, in turn, are a function of aerosol size distribution and the spectral reflective indices. Aerosol optical depth and single scattering albedo in the visible are used as the two basic parameters in the atmospheric temperature variation studies. The former parameter is an indicator of the attenuation power of aerosols, while the latter represents the relative strength of scattering and absorption by aerosols. For aerosols with weak absorption, surface temperature decreases as the optical depth increases because of the domination of backscattering. For aerosols with strong absorption, however, warming could occur as the optical depth increases. The objective of the study is to characterize the means, variability, and trends of Greenhouse gases and aerosol properties on a regional basis using data from its baseline observatories in Korea peninsula. A further goal is to understand the factors that control radiative forcing of the greenhouse and aerosol.

• Archives of Plastic Surgery
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• 제42권6호
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• pp.695-703
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• 2015

Background It is still difficult to prevent partial or full-thickness flap necrosis. In this study, the effects of a cream containing menthol and methyl salicylate on the viability of random-pattern skin flaps were studied. Methods Forty female Sprague-Dawley rats were divided into two equal groups. Caudally based dorsal random-pattern skin flaps were elevated, including the panniculus carnosus. In the study group, 1.5 mL of a cream containing menthol and methyl salicylate was applied to the skin of the flap, and saline solution (0.9%) was used in the control group. Upon completion of the experiment, flap necrosis was analyzed with imaging software and radionuclide scintigraphy. Histopathological measurements were made of the percentage of viable flaps, the number of vessels, and the width of the panniculus carnosus muscle. Results According to the photographic analysis, the mean viable flap surface area in the study group was larger than that in the control group (P=0.004). According to the scintigrams, no change in radioactivity uptake was seen in the study group (P>0.05). However, a significant decrease was observed in the control group (P=0.006). No statistically significant differences were observed between the groups in terms of the percentage of viable flaps, the number of vessels, or the width of the panniculus carnosus muscle (P>0.05). Conclusions Based on these results, it is certain that the cream did not reduce the viability of the flaps. Due to its vasodilatory effect, it can be used as a component of the dressing in reconstructive operations where skin perfusion is compromised.

• 방사성폐기물학회지
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• 제12권2호
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• pp.171-178
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• 2014

원전 해체 시 원자력설비는 안전하게 해체되어야 한다. 고리 1호기나 월성 1호기와 같은 노후화된 원전의 경우 곧 원전 해체를 계획하고 있는 대상 원전이지만, 이 원전들의 가동 중단 후 해체 시 선원항 평가 기준, 제염 및 해체 기술 등의 독자적인 국내 기술 확보는 미흡한 실정이다. 본 연구의 목적은 원전 선원항 평가 기술 중 하나로 In-Situ 기법을 이용하여 대형 원전 기기를 직접 측정하여 측정대상체에 대한 선원항 평가방법을 개발하는 것이다. 원자로 헤드를 별도의 해체 없이 이동형 감마핵종분석기를 이용하여 직접 측정법으로 분석하고 간접 측정을 병행하여 측정 결과를 보완하였다. 그리고, 표면오염시료는 방사화학분석을 수행하였다. 분석 결과를 확장하여 원자로의 핵종 재고량을 계산하였다. 본 연구 결과를 토대로 각 핵종별 방사능량 변화에 따라 해체 시점을 결정할 수 있으며, 원전 해체 시 작업자의 피폭 저감에 도움이 될 것으로 기대한다.

• 자원환경지질
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• 제29권4호
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• pp.495-508
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• 1996

This study had three purposes: (1) to investigate dispersion and enrichment level of potentially toxic elements; (2) to identify uranium-bearing minerals in black shales; and (3) to assess the chemical speciation of heavy metals in soils and sediments. Rock, surface soil and stream sediment samples were collected in the Chungjoo area covered with black shales in Korea. These samples were analyzed for multi-elements using INAA and ICP-AES. The maximum abundance of U in black shales is 56 ppm and radioactivity counts up to 240CPM. Molybdenum, V, Ba, Cu, and Pb are enriched in black shales and most of soils show high concentrations of U, Mo, Ba, Cu, Pb and Zn. Concentrations of potentially toxic elements decrease in the order of mountain soil > farmland soil > paddy soil. Enrichment index of soils and sediments are calculated and higher than 1.0 in the black shale area with the highest value of 6.1. In order to identify U-bearing minerals, electron probe micro analysis was applied, and uraninite and brannerite in black shale were found. Uraninite grains are closely associated with monazite or pyrite with the size of $2{\mu}m$ to $10{\mu}m$ in diameter whereas brannerite occurs as $50{\mu}m$ euhedral grains. With the results of sequential extraction scheme, residual fractions of Cu, Pb and Zn in soils are mainly derived from weathering of black shale but Cu, Pb and Zn in sediments are present as non-residual fractions. Lead is predominantly present as oxidizable phase in soils whereas Zn is in exchageable/water-acid soluble phase in sediments.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.418-423
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• 2016

Background: This work was to get information about $^{90}Sr$ contamination of the environment by using soil and moss from selected areas in Jeju Island, Korea. Materials and Methods: The activities of $^{90}Sr$ in soil and moss samples were investigated at nine locations of Jeju island, Korea. The soil samples have been collected at 4 sites of Jeju island during June to August of 2013, analyzed for vertical distribution of $^{90}Sr$ activities. The moss samples have been collected at 5 sites of Jeju island during November of 2011 to June of 2012, and analyzed for radioactive $^{90}Sr$. Results and Discussion: The $^{90}Sr$ vertical concentrations in the investigated soil samples were 2.77 to $18.24Bq{\cdot}kg^{-1}$ in eastern part, 1.69 to $18.27Bq{\cdot}kg^{-1}$ in northern part, 3.76 to $13.46Bq{\cdot}kg^{-1}$ in the western part and 1.09 to $8.70Bq{\cdot}kg^{-1}$ in the southern part of the Mt. Halla in Jeju island, respectively. Activities of $^{90}Sr$ show the highest value at the surface soil and decrease with depth. The activity concentration measured was in the range of 79.6 to $363Bq{\cdot}kg^{-1}$ -dry moss. Conclusion: This material is expected to be basis reference for survey of environmental radioactivity in Jeju Island.