• 한국지진공학회논문집
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• 제6권5호
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• pp.45-51
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• 2002

비선형동적해석을 통하여 RC 입체라멘교에 대한 지진거동특성 및 파괴메카니즘에 관한 연구를 수행하였다. 파이버모델에 기초한 RC 프레임요소를 교각에 도입하여 3차원영역에서 모델링하여 비선형동적해석을 수행하였다. 해석의 정확성을 향상시키기 위하여 균열 진전후 콘크리트와 철근의 부작특성에 의한 재료역학적 특성차이를 고려하기 위하여 파이버는 철근영역(RC zone)과 무근영역(PC zone)으로 영역화하였다. 대상교량은 관성력 중심위치와 교량의 강성중심 위치가 일치하지 않아 비틀림을 동반한 복잡한 지진거동특성을 나타내었다. 이러한 거동특성에 의하여 유연한 교각 옆에 위치하는 상대적 강성이 큰 교각에 과다한 지진하중이 집중되어 파괴에 이르는 것으로 나타났다.

• Natural Product Sciences
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• 제27권3호
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• pp.161-168
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• 2021

The chemical investigation of the 90% EtOH extract from Cicadidae Periostracum led to the isolation and identification of seven known N-acetyldopamine dimers (1-7). These compounds were identified by comparing mass spectrometry data and NMR spectroscopic data with those previously reported. In this study, complete interpretation of 1D and 2D NMR data of 1 and 2 were reported for the first time. In addition, compounds 3 and 4 were isolated from this material for the first time. All isolates were obtained as racemic mixtures, as confirmed by chiral HPLC. Furthermore, we evaluated the neuroprotective activities of compounds 1-7 and found that compounds 1, 5, and 6 significantly attenuated rotenone-induced death of SH-SY5Y neuroblastoma cells at a concentration of 100 μM. Parallel to this result, compounds 3 and 6 displayed antioxidant effects in the cytoplasm, as determined by CM-H2DCFDA fluorescence intensity, while compounds 1 and 5 showed antioxidant effects in the mitochondria, as assessed by MitoSox fluorescence intensity. Overall, these results suggest that some of these compounds protect neuroblastoma cells by ameliorating the release of reactive oxygen species. Further studies are warranted to elucidate the underlying mechanisms by which these compounds exhibit antioxidant and neuroprotective actions.

• 물과 미래
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• 제52권8호
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• pp.56-66
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• 2019

Nepal is bestowed with abundant water. With more than 1500 mm average annual rainfall in the country, a vast quantity of underutilized groundwater in the Terai belt, and the water stored in snowcaps in the Himalayas, aquifers in the mountains and glacial lakes, Nepal is potentially in an advantageous position in terms of per capita availability. However, low emphasis in management aspect of water and high emphasis in infrastructural developments related to water resources management has resulted in conversion of water in Nepal from a resource to a burden. The global climate change, reduction in number of rainy days, increase in intensity of rainfall during wet monsoon season, encroachment of river banks for settlement, inadequate release of environmental flows from hydropower plants, and attempt to tame the mighty and high velocity rivers of Nepal have resulted in increasing number of water induced disasters (flood and landslide), rise in conflict between local residents and hydropower developers, higher number of devastating landslides, and in some extreme cases mass migration of residents resulting in climate refugees. There is a ray of hope; the awareness level of the people regarding sustainable use of water resources is increasing, the benefit sharing mechanism is gradually being implemented, the role of interdisciplinary and integrated water resources management is appreciated at a higher level and the level of preparedness against flood and landslides is at a higher degree compared to a couple of decades ago. With the use of renewable energy sources, the possibilities for sustainable and productive use of water are on the rise in Nepal.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.2088-2095
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• 2023

The safety of nuclear installations is largely determined by the tightness of fuel elements cladding. As the Fukushima nuclear accident showed, the main task in case of loss of power supply is to ensure reliable removal of residual heat release from spent fuel pool (SFP) with irradiated fuel assemblies (IFAs). The paper presents the results of calculated-experimental studies and thermal-hydraulic modeling of temperature storage modes of IFAs in SFP. Experimental studies of SFP's temperature regime and calculated evaluation of residual heat removal due to the thermal conductivity of building structures surrounding the SFP were performed. To ensure the safe operation of research reactors, it's necessary to know the IFA's residual heat power (RHP) in the reactor and SFP, which is determined depending on the operating time of fuel assemblies (FAs) and the IFAs calculated holding time. The FAs operating time depends on the reactor energy output. The IFAs calculated holding time is determined by the fuel burnup, U-235 mass in the fuel, and reactor utilization factor. The IFAs fuel burnup was calculated using the MCU-PTR program. Also presented are the RHP's calculation results using some of the empirical dependencies. The concept of a passive heat removal system (PHRS) based on thermosyphon's operating principle was proposed.

• Geomechanics and Engineering
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• 제14권5호
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• pp.421-428
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• 2018

In deep mining, the lateral deformation of strip coal pillar appears to be a new characteristic. In order to study the lateral deformation of coal-mass, a monitoring method and monitoring instrument were designed to investigate the lateral deformation of strip coal pillar in Tangkou Coalmine with the mining depth of over 1000 m. Because of without influence of repeated mining, the bedding sandstone roof is easy to break and the angle between maximum horizontal stress and the roadway is small, the maximum lateral deformation is only about 287 mm lower than the other pillars in the same coalmine. In deep mining, the energy accumulation and release cause a discontinuous damage in the heterogeneous coal-mass, and the lateral deformation of coal pillar shows discontinuity, step and mutation characters. These coal-masses not only show a higher plasticity but also the high brittleness at the same time, and its burst tendency is more obvious. According to the monitoring results and theoretical calculations, the yield zone of the coal pillar width is determined as 15.6 m. The monitoring results presented through this study are of great significance to the stability analysis and design of coal pillar.

• 한국동물학회지
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• 제39권2호
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• pp.132-138
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• 1996

To learn how maximal locomotory speed of animals is defined in terms of hindlimb structure and muscle contractile function, take-off speed, hindlimb length, thigh muscle mass, shortening velocity and power of the sastrocnemius muscle were measured with one fast species, Rono nigromaculota and one relatively slowresponding species, Bombina orientalis. Take-off speed (m.sec-1) was greater in R. nigromoculata $(2.4\pm0.2SD, $ n: 14) than in the Bombino $(1.6\pm0.1SD, $ n=8). Stvle of the take-off response was a long-iump type in the Rano and a short-ranged hopping in the Bombing. Faster take-off capacity of the ranid frogs was supported by the longer hindlimb length (relative to body length) and the more massive thigh muscles (relative to body mass), compared to the Bombina. Further, the ranids exhibited faster maximal shortening velocity and Breater maximal power generateion than the Bombina [Vmax $(ML.sec-1)=11.79\pm1.69SD$ for the Runa and $9.74\pm1.27SD$ for the Bombina; Pmax $nW.kg-1)=222.42\pm42.42SD$ for the Rono and $169.03\pm34.52SD$ for the Bombinal. With more massive thigh muscles and greater mechanical power, the ranids would generate greater total power and thus higher energy release per unit time to muscle tissues for the burst take-off. As a consequence, biomechanical properties seen in the ranids seem to be more effective for frost take-off than in the Bombina.

• Nuclear Engineering and Technology
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• 제16권3호
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• pp.169-179
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• 1984

FIPREL 전산코드를 사용하여 원자로 냉각수 내의 핵분열 생성물에 의한 방사능을 분석함으로써 PWR의 운전시에 발생하는 핵연료 피복관 파손을 평가할 수 있는 효과적인 절차를 모색하였다. 이 코드를 이용하여 핵연료의 농축도, 연소도, 가동온도 및 갭유출계수의 크기로 정량화되는 실제적 파손 크기등의 물리적 파라미터에 대해서 핵분열 생성물의 방사능이 나타내는 민감도에 대한 방대한 계산을 실시하였으며 그 결과는 PROFIP방법에 의한 것과 대체적으로 일치한다. 노출 우라늄이 존재하는 경우에는 옥소보다도 화학적으로 더 안정된 핵종간의 방사능비에 근거하여 반복계산을 실시함으로써 파손된 핵연료 봉에서 유출된 방사능만을 분리해 낸다. 개발된 전산코드로 파손 핵연료봉의 선형출력 밀도, 갯수, 실제적 파손 크기 및 노출우라늄의 질량등을 계산할 수 있다. 고리 1호기의 4주기에 걸친 운전 경험을 이 모텔에 의해 분석한 결과에 의하면 본 모델은 원자력발전소 정상운전시 핵연료봉의 상태를 감시·평가하는데 아주 적합한 것으로 판명되었다.

• Nuclear Engineering and Technology
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• 제50권2호
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• pp.268-279
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• 2018

The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and AREVA NP within the PLEIADES software environment models the behavior of fuel rods during irradiation in commercial pressurized water reactors (PWRs), power ramps in experimental reactors, or accidental conditions such as loss of coolant accidents or reactivity-initiated accidents (RIAs). As regards the latter case of transient in particular, ALCYONE is intended to predictively simulate the response of a fuel rod by taking account of mechanisms in a way that models the physics as closely as possible, encompassing all possible stages of the transient as well as various fuel/cladding material types and irradiation conditions of interest. On the way to complying with these objectives, ALCYONE development and validation shall include tests on $PWR-UO_2$ fuel rods with advanced claddings such as M5(R) under "low pressure-low temperature" or "high pressure-high temperature" water coolant conditions. This article first presents ALCYONE V1.4 RIA-related features and modeling. It especially focuses on recent developments dedicated on the one hand to nonsteady water heat and mass transport and on the other hand to the modeling of grain boundary cracking-induced fission gas release and swelling. This article then compares some simulations of RIA transients performed on $UO_2$-M5(R) fuel rods in flowing sodium or stagnant water coolant conditions to the relevant experimental results gained from tests performed in either the French CABRI or the Japanese NSRR nuclear transient reactor facilities. It shows in particular to what extent ALCYONE-starting from base irradiation conditions it itself computes-is currently able to handle both the first stage of the transient, namely the pellet-cladding mechanical interaction phase, and the second stage of the transient, should a boiling crisis occur. Areas of improvement are finally discussed with a view to simulating and analyzing further tests to be performed under prototypical PWR conditions within the CABRI International Program. M5(R) is a trademark or a registered trademark of AREVA NP in the USA or other countries.

• 한국해양환경ㆍ에너지학회지
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• 제13권4호
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• pp.279-287
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• 2010

고성만 해역의 수질 특성 및 정체성을 알기 위해 1987년~2009년간의 만내 1개 정점에 대한 표.저층 수질에 대한 장기관측 자료를 분석하였다. 그 결과 고성만 해역의 수질은 chlorophyll-a, DIP, DIN을 기준으로 중영양(Mesotrophic) 단계이고, 화학적산소요구량(COD) 기준으로 해역등급 2등급으로 볼 수 있어, 고성만은 만내에 유입된 물질수지의 확산이 비교적 더딘 폐쇄성 내만임에도 불구하고 수질은 비교적 양호한 것으로 판단된다. 조사기간 전 기간에 걸친 수질성분에 대해 이동평균 시계열분석, 상관분석 및 회귀분석한 결과 고성만 해역은 시간의 경과에 따라 용존무기인(DIP)은 축적되고, 용존무기질소(DIN)는 감소하는 추세를 보였다. 또한 고성만 해역의 식물성플랑크톤 성장의 제한인자는 용존무기질소(DIN)이고, chlrophyll-a의 농도는 8월의 $4.60{\mu}g/L$로 가장 높았다. 계절 평균 및 계절지수는 11월이 가장 높아 고성만의 영양염 수지는 담수 등에 의한 외부유입보다 만의 내부 즉 수산생물의 대량 양식 및 저층 퇴적물에서의 용출 등이 더 큰 요인으로 작용하는 특징을 보였다. 따라서 고성만 해역의 수질 또는 해역 관리를 위해서는 목적에 따라 동 해역의 용존무기인(DIP), 용존무기질소(DIN) 등의 영양염 수지에 대한 고려가 필요한 것으로 보여진다.

• 방사성폐기물학회지
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• 제10권4호
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• pp.295-303
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• 2012

한국원자력연구원의 지하처분연구시설인 KURT 주변의 지하수 유동 환경과 관련하여 수집 및 분석된 자료를 바탕으로, 가상의 처분장에서 누출된 방사성 핵종의 이동 현상을 시간 영역(time domain)에서 계산하였다. KURT에서 실시된 현장 시험에서 밝혀진 수리지질학적 특성을 바탕으로 지하수 유동 모의를 실시하였고, 그 결과를 통해 파악된 지하수 유동 경로를 따라 방사성 핵종이 이동하는데 걸리는 시간은 시간 영역에서 용질 이동 모의를 하는 TDRW(Time Domain Random Walk) 방식을 통해 평가하였다. 이류(advection)와 분산(dispersion) 현상 외에 방사성 핵종의 붕괴(decay), 평형 흡착(equilibrium sorption), 암반 기질로의 확산(matrix diffusion) 현상이 용질의 이동 시간에 영향을 주는 것으로 설정되었다. 모의 결과를 통해 방사성 핵종과 지하 매질의 특성에 의한 흡착 현상, 기질 확산 현상이 핵종 이동에 미치는 영향이 분석되었으며, 방사성 핵종의 연쇄 KURT 부지 환경에 위치한 가상의 처분 시설에서 누출되는 방사성 핵종의 이동을 Time Domain에서 해석하는 방법에 관한 연구 반응에 의한 영향도 평가하였다. KURT 부지 환경에서 지표로 유출될 수 있다고 계산된 방사성 핵종의 유출량은 처분장에서 누출될 수 있는 양의 $10^{-3}$배 미만이었고, 암반 기질로의 확산 및 흡착이 고려되면 그 비율이 더욱 낮아졌다. 본 연구에서 사용된 핵종 이동 모의 방법은 방사성붕괴나 흡착, 확산 등 이동 지연 현상을 고려하면서 핵종의 이동 시간을 계산할 수 있어 안전성 평가에서 요구되는 심부 지하에서의 방사성 핵종 이동 관련 자료를 작성하는데 활용될 수 있을 것이다.