• Proceedings of the Korean Vacuum Society Conference
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• 2016.02a
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• pp.134-134
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• 2016

CMC(Ceramic Matrix Composites)는 $1500^{\circ}C$ 이상의 고온에서 내열성, 내산화성, 내식성이 우수하여, 초음속 비행체, 가스터빈 엔진 및 원자로용 초고온 부품 등에 수요가 증가하고 있다. 하지만 이러한 특성은 비산소 환경에 국한되는 것으로 약 $400^{\circ}C$ 이상의 산화 분위기에는 탄소섬유가 산화되는 문제로 인하여 적용의 한계를 가지고 있다. 따라서 CMC의 적용범위 확대를 위하여 내산화 코팅으로 CMC의 초고온 산화특성을 개선하는 것이 필수적이며, 장시간 초고온 산화환경 분위기에서 사용되기 위하여 안정적인 코팅기술이 최근 기술개발의 핵심현안으로 부각되고 있다. 본 연구에서는 pack cementation 공정을 이용하여 내산화성이 우수한 SiC 코팅층을 제조하였다. Pack cementation 공정에 사용된 코팅 분말은 57wt.% SiC, 30wt.% Si, 3wt.% B, 10wt.% Al2O3의 비율로 혼합된 것이다. 실험은 3D 직조된 CMC 모재를 혼합분말 내에 침적한 후, Ar 분위기에서 $1600^{\circ}C$, 4~12시간 반응시켜 수 마이크론 두께의 SiC 코팅층을 형성하였다. 더 우수한 산화 특성을 부여하기 위하여 pack 처리된 CMC 표면에 초고온 세라믹인 TaC 소재를 진공플라즈마 코팅 공정으로 적층시켰다. 제조된 코팅층을 SEM, XRD를 이용하여 미세구조 및 결정구조를 분석하였으며, pack cementation에 따른 내산화 특성을 비교 분석하고자 $2000^{\circ}C$에서 산화 실험을 진행하였다. 산화 실험 이후 미세구조 및 결정구조 분석으로 산화거동을 규명하고자 하였다.

• Vacuum Magazine
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• v.3 no.4
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• pp.14-18
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• 2016

In this article, we will summarize recent advances in ultrahigh vacuum (UHV) low-temperature scanning tunneling microscopy (STM) during the last decade. Leading STM groups have finished or are constructing UHV milli-Kelvin high magnetic field STM capable of a few tens of milli-Kelvin and ~ 10 tesla. Applications with UHV sub-Kelvin high magnetic STM have been increased since mid-2000's. Active research using UHV low temperature tuning fork atomic force microscopes and UHV photon low-temperature scanning tunneling microscopes will be introduced. Considering these advances of UHV low-temperature STM we will discuss next trend in STM in the near future.

• Electrical & Electronic Materials
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• v.7 no.2
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• pp.130-137
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• 1994

Indium, element of group III, was refined by using zone refining for high purity refinement. We have found the impurities of T1, Zn, Fe, Cd, Pb, Ni, Cu, Sn in the refined indium with ICP-AES, so that 3.9 weight ppm of T1 was reduced to less than 1 ppm, 1.0 weight ppm of Zn was reduced to 0.7 ppm, 2.8 weight ppm of Cd was reduced to 2.5 ppm and 14.0 weight ppm of Sn was reduced to 6.7 ppm with 5 melten zone passes only. 3.9 weight ppm of T1 was reduced to less than 1 ppm, 1.0 weight ppm of Zn was reduced to 0.3 ppm, 2.8 weight ppm of Cd was reduced to less than 1.0 ppm and 14.0 weight ppm of Sn was reduced to 0.4 ppm after vacuum baking with 5 melten zone passes. The surface morpholgy of metal Indium thin film in each conditions showed that porosities were reduced in the front of sampled ingot after vacuum baking with 5 zone melten zone passes. The average electrical resistivity of Indium thin film was reduced from 1.4*10$^{-3}$ .ohm.-cm in Indium origin ingot to 7.9*10$^{-6}$ .ohm.-cm after zone refined with 5 melten zone passes.

• Transactions of the Korean Society for Noise and Vibration Engineering
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• v.26 no.5
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• pp.552-558
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• 2016

A control rod drive mechanism(CRDM) is a reactor regulating system, which inserts, withdraws or maintains a control rod within a reactor core to control the reactivity of the core. The CRDM for Jordan Research and Training Reactor with 5MW power has been designed and fabricated based on the HANARO’s experience through KAERI and DAEWOO consortium. This paper describes the seismic test results to demonstrate the operability, the drop performance and the structural integrity of CRDM during or after seismic excitations. The seismic tests are carried out under 5 OBE and 1 SSE loads at three Test Rigs simulating the reactor structure and the pool top. From the tests, the CRDM is smoothly driven without a malfunction of stepping motor under OBE load. The pure drop time under OBE and SSE loads is measured as 1.169s and 1.855s to meet the design requirement. Also, it is found that the CRDM maintains the structural integrity without a change of the function and natural frequency before and after seismic loads.

• 한국신재생에너지학회:학술대회논문집
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• 2011.11a
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• pp.84.2-84.2
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• 2011

In this research, two thin film deposition techniques, Atomic Layer Deposition and Sputtering are carried out for the fabrication of Yittria Stabilized Zirconia electrolyte for thin film Solid Oxide Fuel Cell. Zirconium to Yittrium ratio for both cases is about 1/8. Scanning Electron Microscope(SEM) image shows that the growth rate per hour for Atomic Layer Deposition is faster than for sputtering. X-ray Photo-electron Spectroscopy(XPS) shows that the peaks of both Zirconia and Yittria shift towards higher bending energy for the case of Atomic Layer deposition and thus are more strongly attached to the substrate. Later, Nyquist plot was used to compare the conductivity of Yittria Stabilized Electrolyte for both cases. The conductivity at $300^{\circ}C$ for Atomic Layer Deposited Yittria Stabilized Zirconia is found to be $5{\times}10^{-4}S/cm$ while that for sputtered Yittria Stabilized Zirconia is $2{\times}10^{-5}S/cm$ at the same temperature. The reason for better performance for Atomic Layered YSZ is believed to be the Nano-structured layer fabrication that aids in along the plane conduction as compared to the columnarly structured Sputtered YSZ.

• Proceedings of the Korean Vacuum Society Conference
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• 2012.02a
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• pp.379-379
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• 2012

본 연구에서는 고품질의 ZnO 박막을 제작하기 위해 사파이어 기판 위에 ZnO 박막을 Pulsed Laser Deposition (PLD) 법으로 성장하였다. 레이저 에너지 밀도와 펄스주파수를 고정시켰으며, 성장온도와 산소 분압은 각각 $450{\sim}600^{\circ}C$ 및 5~20 sccm으로 변화를 주어 성장 온도와 산소 분압이 박막 특성에 미치는 영향을 분석하였다. 제작된 박막의 전기적 특성을 측정한 결과 성장온도의 증가에 따라 캐리어 농도는 $9.18{\times}10^{18}cm^{-3}$에서 $3.9{\times}10^{16}cm^{-3}$까지 감소하였고, 캐리어 이동도는 $0.95cm^2/Vs$에서 $8.47cm^2/Vs$ 까지 증가하는 경향을 나타내었으며, 산소분압의 변화에는 특정 임계조건을 갖는 것을 확인하였다. 이러한 이유는 PLD 법 성장 메커니즘에서 플라즈마 플럼(plasma flume) 내에 결합된 ZnO 분자가 기판으로 직접 성장이 이루어지는 과정에서 성장 온도가 증가함에 따라 플럼 내에서 결합 된 ZnO 분자의 열적 안정성이 향상되었으며, 유입되는 산소량의 감소로 인해 원자들의 표면 확산 거리 및 확산 시간이 길어져 보다 안정적인 박막 형성에 기인한 것으로 보인다.

• Proceedings of the Korean Vacuum Society Conference
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• 2013.02a
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• pp.321-321
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• 2013

열전재료는 열과 전기의 변환이 상호 가역적으로 일어나는 현상을 갖는 재료로서, 사용온도별로 여러 가지 재료가 개발되고 있다. 중온 영역에서 우수한 열전특성을 보이는 skutterudite는 격자 내에 2개의 공극을 갖고 있고 이에 적절한 원자를 충진하여 포논산란을 유도하고, PGEC(phonon-glass and electron-crystal) 개념을 적용하여 재료의 열적인 성질과 전기적인 성질을 동시에 제어함으로써 열전성능의 향상을 도모할 수 있는 재료이다. 본 연구에서는 챔버 내부 기체를 연속적으로 뽑아내어 진공도를 유지하는 방식이 아닌, 석영관을 앰플화한 진공밀폐 용해법을 사용하였다. 진공밀폐 용해법은 성분원소의 산화와 휘발을 억제하는데 있어 매우 유용한 공정이다. 용해를 통해 얻어진 잉곳을 용해와 동일한 방법으로 석영관에 밀봉하여 873 K에서 100시간 동안 진공열처리를 실시하였다. 또한, 합성된 잉곳의 기계적 특성 향상을 위해 $75{\mu}m$ 이하로 파쇄하여 진공 열간 압축 소결하였다. La가 충진된 $La_zCo_4Sb_{12}$ Skutterudites 단일상을 합성하여 La의 충진량(z)에 따른 열전특성과 전자이동특성을 조사하였다.

• Journal of the Korean Society of Safety
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• v.34 no.3
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• pp.102-110
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• 2019

This paper describes the work and results of the preliminary Probabilistic Safety Assessment (PSA) for a research reactor in the design phase. This preliminary PSA was undertaken to assess the level of safety for the design of a research reactor and to evaluate whether it is probabilistically safe to operate and reliable to use. The scope of the PSA described here is a Level 1 PSA which addresses the risks associated with core damage. After reviewing the documents and its conceptual design, eight typical initiating events are selected regarding internal events during the normal operation of the reactor. Simple fault tree models for the PSA are developed instead of the detailed model at this conceptual design stage. A total of 32 core damage accident sequences for an internal event analysis were identified and quantified using the AIMS-PSA. LOCA-I has a dominant contribution to the total CDF by a single initiating event. The CDF from the internal events of a research reactor is estimated to be 7.38E-07/year. The CDF for the representative initiating events is less than 1.0E-6/year even though conservative assumptions are used in reliability data. The conceptual design of the research reactor is designed to be sufficiently safe from the viewpoint of safety.

• Journal of the Korean Society of Safety
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• v.36 no.3
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• pp.66-73
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• 2021

This report documents the results of an at-power internal events Level 1 Probabilistic Safety Assessment (PSA) for a Korea research reactor (KRR). The aim of the study is to determine the accident sequences, construct an internal level 1 PSA model, and estimate the core damage frequency (CDF). The accident quantification is performed using the AIMS-PSA software version 1.2c along with a fault tree reliability evaluation expert (FTREX) quantification engine. The KRR PSA model is quantified using a cut-off value of 1.0E-15/yr to eliminate the non-effective minimal cut sets (MCSs). The final result indicates a point estimate of 4.55E-06/yr for the overall CDF attributable to internal initiating events in the core damage state for the KRR. Loss of Electric Power (LOEP) is the predominant contributor to the total CDF via a single initiating event (3.68E-6/yr), providing 80.9% of the CDF. The second largest contributor is the beam tube loss of coolant accident (LOCA), which accounts for 9.9% (4.49E-07/yr) of the CDF.

• Journal of the Korean Society of Safety
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• v.37 no.2
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• pp.43-53
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• 2022

This paper describes an attempt to improve and optimize the operational safety level of a domestic research reactor by conducting a probabilistic safety assessment (PSA) under full-power operating conditions. The PSA was undertaken to assess the level of safety at an operating research reactor in Korea, to evaluate whether it is probabilistically safe and reliable to operate, and to obtain insights regarding the requisite procedural and design improvements for achieving safer operation. The technical objectives were to use the PSA to identify the accident sequences leading to core damage, and to conduct sensitivity analyses based thereon to derive insights regarding potential design and procedural improvements. Based on the dominant accident sequences identified by the PSA, eight types of sensitivity analysis were performed, and relevant insights for achieving safer operation were derived. When these insights were applied to the reactor design and operating procedure, the risk was found to be reduced by approximately ten times, and the safety was significantly improved. The results demonstrate that the PSA methodology is very effective for improving reactor safety in the full-power operating phase. In particular, it is a highly suitable approach for identifying the deficiencies of a reactor operating at full power, and for improving the reactor safety by overcoming those deficiencies.