• Nuclear Engineering and Technology
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• 제47권1호
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• pp.11-25
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• 2015

The accident at Japan's Fukushima Daiichi nuclear power plant in March 2011, caused by an earthquake and a subsequent tsunami, resulted in a failure of the power systems that are needed to cool the reactors at the plant. The accident progression in the absence of heat removal systems caused Units 1-3 to undergo fuel melting. Containment pressurization and hydrogen explosions ultimately resulted in the escape of radioactivity from reactor containments into the atmosphere and ocean. Problems in containment venting operation, leakage from primary containment boundary to the reactor building, improper functioning of standby gas treatment system (SGTS), unmitigated hydrogen accumulation in the reactor building were identified as some of the reasons those added-up in the severity of the accident. The Fukushima accident not only initiated worldwide demand for installation of adequate control and mitigation measures to minimize the potential source term to the environment but also advocated assessment of the existing mitigation systems performance behavior under a wide range of postulated accident scenarios. The uncertainty in estimating the released fraction of the radionuclides due to the Fukushima accident also underlined the need for comprehensive understanding of fission product behavior as a function of the thermal hydraulic conditions and the type of gaseous, aqueous, and solid materials available for interaction, e.g., gas components, decontamination paint, aerosols, and water pools. In the light of the Fukushima accident, additional experimental needs identified for hydrogen and fission product issues need to be investigated in an integrated and optimized way. Additionally, as more and more passive safety systems, such as passive autocatalytic recombiners and filtered containment venting systems are being retrofitted in current reactors and also planned for future reactors, identified hydrogen and fission product issues will need to be coupled with the operation of passive safety systems in phenomena oriented and coupled effects experiments. In the present paper, potential hydrogen and fission product issues raised by the Fukushima accident are discussed. The discussion focuses on hydrogen and fission product behavior inside nuclear power plant containments under severe accident conditions. The relevant experimental investigations conducted in the technical scale containment THAI (thermal hydraulics, hydrogen, aerosols, and iodine) test facility (9.2 m high, 3.2 m in diameter, and $60m^3$ volume) are discussed in the light of the Fukushima accident.

• 한국군사과학기술학회지
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• 제27권1호
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• pp.8-14
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• 2024

In this study, the scale of renewable photovoltaic(PV) panels and hydrogen fuel storage facilities required to achieve "net zero carbon emissions" in military facilities were predicted based on actual electricity consumption. It was set up to expect the appropriate installation size of PV panel and hydrogen fuel storage facility for achieving carbon neutrality, limited to the electricity consumption in the public sector, including national defense and social security administration in Yeongcheon. The experimental results of this paper are largely composed of two parts. First, representative meteorological factors were considered to predict solar power generation in the Yeongcheon area, and solar power generation was estimated through a multiple regression model using deep learning techniques. Second, the size of solar power generation facilities and hydrogen storage facilities in military bases was estimated with the amount of solar power generation and electricity consumption. As a result of this analysis, it was calculated that a site of 155.76×104 m² for PV panels was needed and a facility capable of storing 27,657 kg of hydrogen gas was required. Through these results, it is meaningful to demonstrated the prospect that military units can lead the achievement of "carbon net zero 2050" by using PV panels and hydrogen fuel storage facilities on idle sites of military bases.

• 한국해양환경ㆍ에너지학회지
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• 제3권2호
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• pp.25-32
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• 2000

내화용 오일붐은 해상누유사고시 누유현장소각기술에 있어서 핵심적인 방제장비이다. 본 논문에서는 내화용 오일붐의 성능평가기법으로 전기로시험과 수조시험을 제안하였다. 전기로시험에는 내화용 재질의 내화성을 평가하며, 수조시험에서는 실제 현장소각시에 화염에 노출된 내화용 오일붐의 상태를 최대한 모사하였다. 수조시험장비는 유조, 내화용 오일붐 모형, 연소가스 흡입을 위한 후드, 소각로와 온도계 등으로 구성된다. 본 연구에서 개발된 내화용 오일붐에 대하여 성능평가를 수행한 결과, 화염온도 800℃에 대하여 견딜 수 있음을 확인할 수 있었다. 본 연구의 성능평가기법이 실제 해상에서 사용할 수 있는 내화용 오일붐에 대하여 적용할 수 있기 위해서는 보다 더 높은 측도의 시험시설 및 장시간의 실험이 요구된다.

• Corrosion Science and Technology
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• 제11권6호
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• pp.213-217
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• 2012

1) 선진 핵연료주기시설 관련 규제기술과 관련하여 인허가 안전심사의 경험이 없으며, 선진 핵연료주기시설 인허가를 위한 규제체계 및 안전성 평가방법 등의 개발이 필요한 단계이며 관련기기와 제반 공정에서 재료의 내식성을 평가하는 기준마련이 시급하다. 2) 선진 핵주기시설 관련 국내 기술수준을 분석하였고 그 핵심 공정인 전해환원, 전해정련, 전해제련공정의 실험변수를 조사하고 평가 필요항목을 정리하였다. 3) 전해환원과 전해정련공정의 경우 Hot-cell 내에 수분 및 산소가 일정 수준 이하로 유지되는 경우, 재료의 부식은 고려하지 않아도 되나 우라늄 잉곳 제조 공정에서 수냉 코일을 사용하게 되는 경우 물에 의한 부식을 고려해야 한다. 4) 전해 제련공정의 경우 LCC, RAR, Cd 증류공정에서 플랜지의 O-ring을 보호하기 위해 수냉 코일을 사용하게 되는 경우 물에 의한 부식을 고려해야 한다.

• 국제초고층학회논문집
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• 제4권1호
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• pp.65-73
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• 2015

Detailed finite element (FE) analyses of a full-scale four-story steel frame structure, subjected to consecutive 60% and 100% excitations from the JR Takatori records during the 1995 Hyogoken-Nanbu earthquake, are conducted using E-Simulator. The four-story frame was tested at the largest shake-table facility in the world, E-Defense, in 2007. E-Simulator is a parallel FE analysis software package developed to accurately simulate structural behavior up to collapse by using a fine mesh of solid elements. To reduce computational time in consecutive dynamic time history analyses, static analysis with gravity force is introduced to terminate the vibration of the structure during the analysis of 60% excitation. An overall sway mechanism when subjected to 60% excitation and a story mechanism resulting from local buckling of the first-story columns when subjected to 100% excitation are simulated by using E-Simulator. The story drift response to the consecutive 60% and 100% excitations is slightly smaller than that for the single 100% excitation.

• 한국물환경학회지
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• 제26권6호
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• pp.986-993
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• 2010

Spatially distributed on-site devices such as bioretentions and bioboxfilters are becoming more common as a means of controlling urban stormwater quality. One approach to modeling the cumulative catchment-scale effects of such devices is to resolve the catchment down to the scale of a land parcel or finer, and then to model each device separately. The focus of this study is to propose a semi-distributed model for simulating urban stormwater quantity and identifying best sites for spatially distributed on-site stormwater control devices in an urban drainage system. A detailed model for urban stormwater improvement conceptualization simulation is set up for a $0.9342km^2$.

• 한국신재생에너지학회:학술대회논문집
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• 한국신재생에너지학회 2007년도 추계학술대회 논문집
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• pp.613-616
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• 2007

A pilot scale circulating fluidized bed for refuse derived fuel is developed and constructed in order to demonstrate efficient and safe utilization of waste fuel. The capacity of the facility is 8 steam tons per hour with the steam quality of $450^{\circ}C$ and 38atm. The quantity and the quality of the produced steam is sufficient to produce 1MWe power capacity. The test operation proved the high combustion efficiency of 99% and up. The emissions of NOx, SOx in flue gas are below 100, 60ppm respectively with out any emission control. HCl emissions were above 400ppm at the combustor exit but reduced below 10ppm after scrubber.

• 한국철도학회:학술대회논문집
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• 한국철도학회 2009년도 춘계학술대회 논문집
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• pp.1931-1935
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• 2009

Korean railway network GIS-based information system requires so much cost and time. One of the difficulties is due to the fact that GIS-based information system requires the feature database for GIS, which is generally built manually from many as-built drawing files. In order to build-up database automatically Using GPS coordinates, this study suggests the automatic data conversion from electronic drawings to make feature database for GIS. The proposed method can be applied to build large-scale railway facility management system.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1310-1319
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• 2024

The reactor cavity cooling system (RCCS) is a passive reactor safety system commonly present in the designs of High-Temperature Gas-cooled Reactors (HTGR) that removes heat from the reactor pressure vessel by means of natural convection and radiation. It is one of the factors responsible for ensuring that the reactor does not melt down under any plausible accident scenario. For the simulation of accident scenarios, which are transient phenomena unfolding over a span of up to several days, intermediate fidelity methods and system codes must be employed to limit the models' execution time. These models can quantify radiation heat transfer well, but heat transfer caused by natural convection must be quantified with the use of correlations for the heat transfer coefficient. It is difficult to obtain reliable correlations for HTGR RCCS heat transfer coefficients experimentally due to such a system's size. They could, however, be obtained from high-fidelity steady-state simulations of RCCSs. The Rayleigh number in RCCSs is too high for using a Direct Numerical Simulation (DNS) technique; thus, a Reynolds-Averaged Navier-Stokes (RANS) approach must be employed. There are many RANS models, each performing best under different geometry and fluid flow conditions. To find the most suitable one for simulating an RCCS, the RANS models need to be validated. This work benchmarks various RANS models against three experiments performed on the HTTR RCCS Mockup by the Japanese Atomic Energy Agency (JAEA) in 1993. This facility is a 1/6 scale model of a vessel cooling system (VCS) for the High Temperature Engineering Test Reactor (HTTR), which is operated by JAEA. Multiple RANS models were evaluated on a simplified 2d-axisymmetric geometry. They were found to reproduce the experimental temperature profiles with errors of up to 22% for the lowest temperature benchmark and 15% for the higher temperature benchmarks. The results highlight that the pragmatic turbulence models need to be validated for high Rayleigh natural convection-driven flows and improved accordingly, more publicly available experimental data of RCCS resembling experiments is needed and indicate that a 2d-axisymmetric geometry approximation is likely insufficient to capture all the relevant phenomena in RCCS simulations.

• 기술혁신학회지
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• 제13권4호
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• pp.700-716
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• 2010

이 논문에서는 탈(脫)추격형 기술혁신의 사례로 1990~2007년에 포스코가 용융환원법을 개발한 과정과 그 특정에 대해 분석하였다. 포스코는 차세대 혁신철강기술의 일환으로 용융환원법에 주목했으며, 푀스트와의 협력을 바탕으로 코렉스 공법을 상용화하는 데 성공하였다. 더 나아가 포스코는 분광석을 원료로 사용할 수 있는 파이넥스 공법을 개발하는 작업을 전개했으며, 그것은 모델 플랜트, 파일럿 플랜트, 데모 플랜트, 상용화 설비의 단계를 거쳤다. 포스코는 파이넥스 공법과 관련된 모든 영역의 기술을 개발 혹은 확보하는 데 성공함으로써 기존의 빠른 추종자를 넘어 기술혁신 선도자로 부상하고 있다. 포스코의 용융환원법 개발과정은 적절한 기술선택, 점진적 규모 확대, 나선형 기술개발방식, 상호보완적 기술협력, 과감한 연구개발투자, 중량급 프로젝트 매니저의 존재, 초기 단계의 정부 지원 등과 같은 특성을 보였다. 이러한 포스코의 용융환원법 사례는 기술패러다임 전환기에 이루어진 경로실현형 기술혁신(path-revealing innovation) 에 해당한다.