• 한국광물학회지
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• 제24권1호
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• pp.19-29
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• 2011

베링해 알류샨 분지의 북부 사면지역에서 채취된 피스톤 코아 PC25A의 퇴적물에서 점토광물의 반정량적 함량 분석을 통해 지난 마지막 빙하기 동안 퇴적물의 기원지와 운송 경로의 변화를 살펴보았다. 코아 PC25A의 연대는 방산충 L. nipponica sakaii의 마지막 출현 시기($48.6{\pm}2\; ka$)와 인근 지역에서 채취한 연대가 잘 정립된 코아 PC23A의 퇴적물 색도($a^{\ast},\; b^{\ast}$) 및 퇴적 엽리층의 대비를 통해 설정되었다. 코아 PC25A의 최하단부가 약 57,600년 전으로 계산되었고, 코아 상부는 손실된 것으로 판단된다. 지난 마지막 빙하기 동안 스멕타이트, 일라이트, 캐올리나이트, 녹니석의 평균 함량은 각각 11% (5~24%), 47% (36~58%), 13% (9~19%), 29% (21~40%)이다. 코아 PC25A의 인근 지역에서 채취한 코아 MC24에서 분석된 홀로세의 점토광물 함량에 비하여 마지막 빙하기동안에 특징적으로 일라이트 함량이 증가하였고 스멕타이트 함량은 감소하였다. 따뜻한 기후의 홀로세 전기(Early Holocene) 동안 일라이트 함량이 높은 점토 퇴적물이 알라스카 대륙의 북부 지역(Province 1)으로부터 유입되는 융빙수에 의해 운반된 것으로 판단된다. MIS 2의 후빙기(B${\phi}$lling-All${\phi}$rod)동안에도 융빙수에 의해 점토광물이 운반되었으나, 일라이트 함량이 홀로 세 전기에 비해 낮기 때문에 북쪽의 Province 1보다는 남쪽에 위치한 Province 2와 Province 3에서 점토입자들이 기원된 것으로 해석된다. 마지막 최대 빙하기(Last Glacial Maximum)동안 나타나는 높은 스멕타이트 함량은 베링해 남동쪽 알라스카 반도 인근 지역(Province 4)에서 공급되는 점토 퇴적물의 양이 증가하였기 때문으로 보인다. MIS 3 초기에서 중기로 가면서 일라이트와 스멕타이트 함량이 감소하고, 녹니석의 함량은 증가하였다. MIS 3 동안 해수면이 낮아지면서 Province 2와 Province 3에서 점토 퇴적물의 공급이 증가한 것으로 보인다. 베링해 알류산 분지의 북부 사면지역에서 채취된 코아 PC25A에서 분석된 점토광물 조성의 변화는 마지막 빙하기동안 해수면의 하강으로 인하여 점토광물의 이동과 관련된 베링해의 표층 해류 순환이 현재와는 다른 양상으로 변화되었기 때문이다.

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1537-1546
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• 2017

Many thermal-hydraulic tests have been conducted at the Korea Atomic Energy Research Institute for verification of the SMART (System-integrated Modular Advanced ReacTor) design, the standard design approval of which was issued by the Korean regulatory body. In this paper, the contributions of these tests to the standard design approval of SMART are discussed. First, an integral effect test facility named VISTA-ITL (Experimental Verification by Integral Simulation of Transients and Accidents-Integral Test Loop) has been utilized to assess the TASS/SMR-S (Transient and Set-point Simulation/Small and Medium) safety analysis code and confirm its conservatism, to support standard design approval, and to construct a database for the SMART design optimization. In addition, many separate effect tests have been performed. The reactor internal flow test has been conducted using the SCOP (SMART COre flow distribution and Pressure drop test) facility to evaluate the reactor internal flow and pressure distributions. An ECC (Emergency Core Coolant) performance test has been carried out using the SWAT (SMART ECC Water Asymmetric Two-phase choking test) facility to evaluate the safety injection performance and to validate the thermal-hydraulic model used in the safety analysis code. The Freon CHF (Critical Heat Flux) test has been performed using the FTHEL (Freon Thermal Hydraulic Experimental Loop) facility to construct a database from the $5{\times}5$ rod bundle Freon CHF tests and to evaluate the DNBR (Departure from Nucleate Boiling Ratio) model in the safety analysis and core design codes. These test results were used for standard design approval of SMART to verify its design bases, design tools, and analysis methodology.

• Journal of Welding and Joining
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• 제21권2호
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• pp.89-96
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• 2003

The change of microstructures in the base metal during transient liquid phase bonding process of directionally Ni base superalloy, GTD-111 was investigated. Bonds were fabricated using a series of holding times(0-7.2ks) at three different temperatures(1403, 1418 and 1453K) under a vacuum of 13.3mPa. In raw material, ${\gamma}$- ${\gamma}$' eutectic phases, platelet η phases, MC carbide and PFZ were seen in interdendritic regions or near grain boundary and size of primary ${\gamma}$' precipitates near interdendritic regions were bigger than core region. The primary ${\gamma}$' precipitates in dendrite core were dissolved early in bonding process, but ${\gamma}$' precipitates near interdendritic regions were dissolved partially and shape changed. The dissolution rate increased with increasing temperature. Phases in interdendritic regions or near pain boundary continually changed with time at the bonding temperature. In the bonding temperature of 1403K, eutectic phases had not significantly changed, but η phases had transformed from platelet shape to needle morphology and PFZ region had widened with time. The interdendritic region and near pain boundary were liquated partially at 1423k and fully at 1453k by reaction of η phases and PFZ. In the bonding temperature of 1453K, interdendritic region and near pain boundary were liquated and then new phases which mixed with η phases, PFZ and MC carbide crystallized during cooling. Crystallized η phases transformed from rod shape to platelet shape with increasing holding time.

• Nuclear Engineering and Technology
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• 제48권1호
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• pp.16-25
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• 2016

In severe loss of coolant accidents (LOCA), similar to those experienced at Fukushima Daiichi and Three Mile Island Unit 1, the zirconiumalloy fuel claddingmaterials are rapidlyheateddue to nuclear decay heating and rapid exothermic oxidation of zirconium with steam. This heating causes the cladding to rapidly react with steam, lose strength, burst or collapse, and generate large quantities of hydrogen gas. Although maintaining core cooling remains the highest priority in accident management, an accident tolerant fuel (ATF) design may extend coping and recovery time for operators to restore emergency power, and cooling, and achieve safe shutdown. An ATF is required to possess high resistance to steam oxidation to reduce hydrogen generation and sufficient mechanical strength to maintain fuel rod integrity and core coolability. The initiative undertaken by Electric Power Research Institute (EPRI) is to demonstrate the feasibility of developing an ATF cladding with capability to maintain its integrity in $1,200-1,500^{\circ}C$ steam for at least 24 hours. This ATF cladding utilizes thin-walled Mo-alloys coated with oxidation-resistant surface layers. The basic design consists of a thin-walled Mo alloy structural tube with a metallurgically bonded, oxidation-resistant outer layer. Two options are being investigated: a commercially available iron, chromium, and aluminum alloy with excellent high temperature oxidation resistance, and a Zr alloy with demonstratedcorrosionresistance.Asthese composite claddings will incorporate either no Zr, or thin Zr outer layers, hydrogen generation under severe LOCA conditions will be greatly reduced. Key technical challenges and uncertainties specific to Moalloy fuel cladding include: economic core design, industrial scale fabricability, radiation embrittlement, and corrosion and oxidation resistance during normal operation, transients, and severe accidents. Progress in each aspect has been made and key results are discussed in this document. In addition to assisting plants in meeting Light Water Reactor (LWR) challenges, accident-tolerant Mo-based cladding technologies are expected to be applicable for use in high-temperature helium and molten salt reactor designs, as well as nonnuclear high temperature applications.

• 전기전자학회논문지
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• 제25권1호
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• pp.95-100
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• 2021

조선소에서 선체 블록과 용접 피더의 위치를 알면 작업자의 위치 정보를 쉽게 얻을 수 있다. 이 데이터는 작업장 안전 모니터링 시스템 구축에 매우 유용하다. 그러나 선체 구조와 용접 공정의 특수성 때문에 작업장에 고정 통신망을 적용하기 어렵다. 본 연구에서는 전용 통신선을 대신할 수 있는 유도 전력선 통신을 선체블록과 같은 금속매체에 적용하는 기술을 검토하였다. 용접기의 전원 케이블에 설치할 유도 결합기로 페라이트 코어를 사용하였고, 금속 블록의 지지대에 체결할 결합기로 나노 결정질 코어를 적용하였다. 제안된 커플러는 COMSOL AC/DC 모듈로 3차원 모델링 하였고 동작 원리를 시각화하기 위하여 유한 요소 해석을 수행하였다. 알루미늄 프로파일을 사용한 금속블록 통신 성능 테스트에서 용접 전극의 블록 접촉으로 통신 채널이 형성되었을 때 대역폭은 6 Mbps 이상 유지되었다.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.2230-2245
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• 2023

KANT (KAIST Advanced Nuclear Tachygraphy) is a PWR core simulator recently developed at Korea Advance Institute of Science and Technology, which solves three-dimensional steady-state and transient multigroup neutron diffusion equations under Cartesian geometries alongside the incorporation of thermal-hydraulics feedback effect for multi-physics calculation. It utilizes the standard Nodal Expansion Method (NEM) accelerated with various Coarse Mesh Finite Difference (CMFD) methods for neutronics calculation. For thermal-hydraulics (TH) calculation, a single-phase flow model and a one-dimensional cylindrical fuel rod heat conduction model are employed. The time-dependent neutronics and TH calculations are numerically solved through an implicit Euler scheme, where a detailed coupling strategy is presented in this paper alongside a description of nodal equivalence, macroscopic depletion, and pin power reconstruction. For validation of the steady, transient, and depletion calculation with pin power reconstruction capacity of KANT, solutions for various benchmark problems are presented. The IAEA 3-D PWR and 4-group KOEBERG problems were considered for the steady-state reactor benchmark problem. For transient calculations, LMW (Lagenbuch, Maurer and Werner) LWR and NEACRP 3-D PWR benchmarks were solved, where the latter problem includes thermal-hydraulics feedback. For macroscopic depletion with pin power reconstruction, a small PWR problem modified with KAIST benchmark model was solved. For validation of the multi-physics analysis capability of KANT concerning large-sized PWRs, the BEAVRS Cycle1 benchmark has been considered. It was found that KANT solutions are accurate and consistent compared to other published works.

• 한국물환경학회지
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• 제29권4호
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• pp.497-503
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• 2013

The morphological characteristics of granules, which were generated in lab-scale sequencing batch reactor (SBR) for simultaneous nitrogen and phosphorus removal with denitrifying phosphorus accumulating organism (dPAO) were identified. Granular sludge was fully developed in the anaerobic-anoxic (An-Ax) SBR after 180 days of SBR operation. The average diameter of granular sludge was 2.2 mm and rod-type organisms dominated in the granules. In addition, about 1.0 mm of white precipitate was observed in the core of the granule, and the material was confirmed that it is very similar to hydroxyapatite $(HAP;\;Ca_5(PO_4)_3(OH))$ by X-ray diffraction) analysis.

• 한국분말재료학회지
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• 제11권1호
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• pp.16-21
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• 2004

The nano-sized Co particles were successfully synthesized by chemical vapor condensation (CVC) process using the precursor of cobalt carbonyl ($Co_2(CO)_8$). The influence of carrier gases on the microstructure and magnetic properties of nanoparticles was investigated by means of XRD, TEM, XPS and VSM. The Co nano-particles with different phases and shapes were synthesized with a change of carrier gas : long string morphologies with coexistence of fcc and hcp structure in Ar carrier gas condition; finer Co core in a mass of cobalt oxide with only fcc structure in He; rod type cobalt oxide phase in Ar＋6vol％$O_2$. The saturation magnetization and coercivity was lower in Co nanoparticles synthesized in He carrier gas, due to their finer size.

• 한국분말재료학회지
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• 제11권4호
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• pp.328-332
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• 2004

Fe nanopowders were successfully synthesized by plasma arc discharge (PAD) process using Fe rod. The influence of chamber pressure on the microstructure was investigated by means of X-ray Diffraction (XRD), Field Emission Scanning Electron Microscope (FE-SEM), Transmission Electron Microscopy (TEM) and X-ray Photoelectron Spectroscopy (XPS). The prepared particles had nearly spherical shapes and consisted of metallic cores (a-Fe) and oxide shells (Fe$_{3}$O$_{4}$), The powder size increased with increasing chamber pressure due to the higher dissolution and ejection rate of H$_2$ and gas density in the molten metal.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 심포지엄 논문집 정보 및 제어부문
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• pp.21-23
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• 2005

NARX(Nonlinear AutoRegressive with eXogenous input) neural network was used for prediction of nuclear reactor behavior which was influenced by control rods in short-term period and also by xenon and boron in long-term period in load following operations. The developed model was designed to predict reactor power, xenon worth and axial offset with different burnup rates when control rod and boron were adjusted in load following operations. Data of UCN 3 were collected by ONED94 code. The test results presented exhibit the capability of the NARX neural network model to capture the long term and short term dynamics of the reactor core and seems to be utilized as a handy tool for the use of a plant simulation.