• 대한전자공학회:학술대회논문집
• /
• 대한전자공학회 1999년도 하계종합학술대회 논문집
• /
• pp.283-286
• /
• 1999

Transparent conductive aluminum-doped ZnO(AZO) films Were prepared by a ultrasonic spray pyrolysis method at the substrate temperature below 23$0^{\circ}C$. A vertical type hot wall furnace was used as a reactor in the deposition system. Zinc acetate dissolved in methanol was selected as a precursor. The substrate temperature was varied from 18$0^{\circ}C$to 24$0^{\circ}C$. Aluminum (Al) was doped into ZnO films by incorporating anhydrous aluminum chloride (AlCl$_3$) in the zinc acetate solution. The proportion of the Al in the starting solution was varied from 0 wt % to 3.0 wt %. The crystallographic properties and surface morphologies of the films were analyzed by X-ray diffraction (XRD) and scanning electron microscopy (SEM), respectively. The resistivity of the films was measured by the Van der Pauw method, and the mobility and carrier concentration were obtained through the Hall effect measurements Transmittance was measured in the visible region. The effects of substrate temperature and aluminum content in the starling solution on the structural and electrical properties of the AZO films are discussed

• 한국유체기계학회 논문집
• /
• 제10권5호
• /
• pp.9-19
• /
• 2007

Fluid temperature fluctuations in a mixing tee pipe were numerically analyzed by LES model in order to clarify internal turbulent flows and to develope an evaluation method for high-cycle thermal fatigue. Hot and cold water with an temperature difference $40^{\circ}C$ were supplied to the mixing tee. Fluid temperature fluctuations in a mixing tee pipe is analysed by using the computational fluid dynamics code, FLUENT, Temperature fluctuations of the fluid and pipe wall measured as the velocity ratio of the flow in the branch pipe to that in the main pipe was varied from 0.05 to 5.0. The power spectrum method was used to evaluate the heat transfer coefficient. The fluid temperature characteristics were dependent on the velocity ratio, rather than the absolute value of the flow velocity. Large fluid temperature fluctuations were occurred near the mixing tee, and the fluctuation temperature frequency was random. The ratios of the measured heat transfer coefficient to that evaluated by Dittus-Boelter's empirical equation were independent of the velocity ratio, The multiplier ratios were about from 4 to 6.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1995년도 추계학술발표회논문집(2)
• /
• pp.680-686
• /
• 1995

It has been known that water-side corrosion of fuel rods in nuclear reactor is accompanied with the loss of metallic wall thickness and pickup of hydrogen. This corrosion is one of the important limiting factors ill the operating life of fuel rods. In connection with the fuel cladding corrosion, a device to measure the water-side oxide layer thickness by means of the eddy-current method without destructing the fuel rod was developed by KAERI. The device was installed on the multi-function testing bench in the nondestructive test hot-cell and its calibration was carried out successfully for the standard rod attached with plastic thin films whose thicknesses are predetermined. It shows good precision within about 10% error. And a PWR fuel rod, one of the J-44 assembly discharged from Kori nuclear power plant Unit-2, has been selected for oxide layer thickness measurements. With the result of data analysis, it appeared that the oxide layer thicknesses of Zircaloy cladding vary with the length of the fuel rod, and their thicknesses were compared with those of the destructive test results to confirm the real thicknesses.

• 열처리공학회지
• /
• 제7권2호
• /
• pp.129-138
• /
• 1994

The purpose of this study is to clarify the influence of the reaction temperature and $AlCl_3$ content on the aluminide coating formation on Ni-based superalloy IN713C in CVD process and to compare its throwing power with that of Pack Cementation process. Aluminide coating was formed by CVD in hot-wall stainless tube reactor from an $AlCl_3-H_2$ mixture in the temperature range $850{\sim}1050^{\circ}C$. At reaction temperature $850^{\circ}C$, the coating thickness and the content of aluminium at the surface were increased as $AlCl_3$ heating temperature was raised. At reaction temperature $1050^{\circ}C$, they were not influenced by the variation of $AlCl_3$ heating temperature. When $AlCl_3$ heating temperature was fixed $125^{\circ}C$, the phases of the coatings were varied from $Ni_2Al_3$ to Al-rich NiAl and to Ni-rich NiAl with the reaction temperature. Therefore, in this study the reaction temperature has been found to be a major factor in determining the phase formed in CVD process. The throwing power of CVD was superior to that of Pack Cementation.

• Nuclear Engineering and Technology
• /
• 제54권5호
• /
• pp.1890-1901
• /
• 2022

We have assessed the applicability of the thermal-hydraulic system analysis code, SPACE, to a small modular reactor called SMART. For the assessment, the experimental data from a scale-down integral-test facility, SMART-ITL, were used. It was conformed that the SPACE code unrealistically calculates the safety injection flow rate through the CMT and SIT during a small-break loss-of-coolant experiment. This unrealistic behavior was due to the overprediction of interfacial heat transfer at the steam-water interface in a vertically stratified flow in the tanks. In this study, a special thermal-hydraulic component model has been developed to realistically calculate the interfacial heat transfer when a strong non-equilibrium two-phase flow is formed in the CMT or SIT. Additionally, we developed a special heat structure model, which analytically calculates the heat transfer from the hot steam to the cold tank wall. The combination of two models for the tank are called the special component model. We assessed it using the SMART-ITL passive safety injection system (PSIS) test data. The results showed that the special component model well predicts the transient behaviors of the CMT and SIT.

• Nuclear Engineering and Technology
• /
• 제42권6호
• /
• pp.662-669
• /
• 2010

To develop the manufacturing methods for the blanket first wall (FW) of the International Thermonuclear Experimental Reactor (ITER) and to verify the integrity of the joint, Be/Cu mockups were fabricated and tested at the KoHLT-1 (Korea Heat Load Test facility), a graphite heater facility located at the Korea Atomic Energy Research Institute (KAERI). Since Be and Cu joining is the focus of the present study, the fabricated mockups had a CuCrZr heat sink joined with three Be tiles as an armor material, unlike the original ITER blanket FW, which has a stainless steel structure and coolant tubes. Hot isostatic pressing (HIP) was carried out at $580^{\circ}C$ and 100 MPa for 2 hours as the method for Be/Cu joining. Three interlayers, namely, $1{\mu}mCr/10{\mu}mCu$, $1{\mu}mTi/0.5{\mu}mCr/10{\mu}mCu$, and $5{\mu}mTi/10{\mu}mCu$ were applied as a coating to the Be tiles by a physical vapor deposition (PVD) method. A shear test was performed with the specimens, which were fabricated by the same methods as those used to fabricate the mockups. The average values were 125 MPa to 180 MPa, and the samples with the $1{\mu}mCr/10{\mu}mCu$ interlayer showed the lowest value. No defect or delamination was found in the joints of the mockups by the developed ultrasonic test using a flat-type probe with a 10 MHz frequency and a 0.25 inch diameter. High heat flux (HHF) tests were performed at $1.0\;MW/m^2$ heat flux for each mockup using the given conditions, and the results were analyzed by ANSYS-CFX code. For the test criteria, an expected fatigue lifetime about 1,000 cycles was obtained by analysis with ANSYS-mechanical code. Mockups using the interlayers of $1{\mu}mTi/0.5{\mu}mCr/10{\mu}mCu$ and $5{\mu}mTi/10{\mu}mCu$ survived up to 1,100 cycles over the required number of cycles. However, one of the Be tiles in the other two mockups using the $1{\mu}mCr/10{\mu}mCu$ interlayer was detached during the screening test, and others were detached by discharge after 862 cycles. The integrity of the joints using the proposed interlayers was proven by the HHF test, but the other interlayer requires more study before it can be used for the joining of Be to Cu. Moreover, it was confirmed that the measured temperatures agreed well with the analysis temperatures, which were used to estimate the lifetime and that the developed facility showed its capability of the long time operation.

• 센서학회지
• /
• 제6권2호
• /
• pp.155-162
• /
• 1997

zinc acetate를 포함하는 용액으로부터 r-plane 사파이어 기판 위에 ZnO 막(膜)을 증착하였다. 초음파(超音波) 발생기(發生器)로 용액을 진동시켜 증기입자를 만든 후 이것을 고온 반응로(反應盧) 내에서 열분해(熱分解) 시켜 막(膜)을 증착하였다. 제조된 막(膜)의 결정성, 표면형태 및 조성을 XRD, SEM 및 AES로 각각 분석하였다. 기판온도가 막(膜)의 특성에 미치는 영향에 대해 조사하였다. 기판온도 $300^{\circ}C$에서 (110) 방향으로 강하게 성장된 막(膜)을 얻을 수 있었다. 구리의 첨가(添加)와 습식산화(濕式酸化)에 의해 막(膜)의 저항율을 $3{\times}10^{6}{\Omega}{\cdot}cm$이상으로 높일 수 있었다.

• 한국진공학회지
• /
• 제18권4호
• /
• pp.318-330
• /
• 2009

본 한국원자력연구원에서는 국제열핵융합실험로(ITER)의 일차벽을 개발하기 위해 그라파이트 히터를 이용한 고열부하 시험시설 KoHLT-1(Korea Heat Load Test facility-1)을 구축하였으며, 현재 정상적으로 가동되고 있다. KoHLT-1의 주목적은 Be-CuCrZr-SS의 이종 금속이 HIP 방법에 의해 접합된 ITER 일차벽 mockup의 접합 건전성을 확인하는데 있다. KoHLT-1은 판형 그라파이트 히터, 냉각 jacket이 부착된 상자형 시험용기, 직류 전원, 냉각계통, He 기체 공급계통과 각종 진단계통으로 구성되어 있으며, 이 모든 시설은 Be 처리가 가능한 특수 정화계통이 설치된 실험실에 설치되었다. 그라파이트 히터는 두개의 시험 대상물 사이에 설치되며, 시험대상물과의 거리는 $2{\sim}3\;mm$이다. 시험 대상물의 크기와 요구되는 열유속에 따라 여러 가지의 그라파이트 히터를 설계, 제작하였으며, 전기 저항은 고온 운전 중에 $0.2{\sim}0.5{\Omega}$이 되도록 하였다. 히터는 100V/400 A의 직류전원에 연결되어 있으며, PC와 multi function module로 구성된 전류 조정계통에 의해 미리 프로그램되어 있는 패턴으로 전류를 자동 조절하게 된다. 두 시험대상물에 인가되는 열유속은 calorimetry법에 의해 냉각수의 입, 출구 온도와 유량을 측정하여 얻게 된다. 여러 가지 형태의 ITER 일차벽 Be mockups에 대해 고열부하 시험을 수행하였으며, 시험을 통하여 KoHLT-1 고열부하 시험 시설의 성능이 확인되었고, 24시간 이상의 연속 운전에 있어서도 그 신뢰성이 입증되었다.