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마이크로파를 이용한 UO<sub>2</sub>+5wt% CeO<sub>2</sub>성형체의 소결특성
정창용,이수철,김시형,김한수,이영우,Joung, Chang-Young,Lee, Su-Cheol,Kim, Si-Hyung,Kim, Han-Soo,Lee, Young-Woo 한국세라믹학회 2004 한국세라믹학회지 Vol.41 No.11
마이크로파 가열장치를 이용하여 마이크로파 조사에 따른 SiC와 MO$_2$ 시료에 대한 발열실험을 수행하였고, 이 실험에서 얻은 발열특성 결과들을 고려하여 $UO_2$+5wt% CeO$_2$ 성형체에 대한 산화소결 실험을 수행하였다. 그리고 마이크로파와 전기로에서 각각 소결된 MO$_2$ 소결체의 특성변화를 비교분석하였다 마이크로파 조사에 따른 MO$_2$시료의 발열온도는 입력전력의 증가에 따라서 급속히 증가하였으며, 출력전력은 주로 보조가열재인 SiC와 MO$_2$ 시료가 마이크로파와 반응하는 정도에 따라서 변하였다. 마이크로파에 의하여 소결된 소결체의 밀도는 전기로에서 동일한 조건으로 소결된 소결체의 밀도보다 약 2% T.D. 낮았다. 소결체의 미세조직은 전기로에서 제조된 소결조직에 비하여 마이크로파에 의해 제조된 소결체의 기공분포가 불규칙적이었으나, 평균결정립 크기는 크게 나타났다. The heat generation tests of SiC and MO$_2$ samples by use of a microwave heating system were carried out and UO$_2$+5 wt% CeO$_2$ pellets were sintered in a microwave furnace in an oxidizing atmosphere, by taking into account the characteristics of the microwave heating obtained from the heat generation tests. The characteristics of pellets sintered in a microwave furnace were analysed and compared with those of the pellets sintered in a conventional electrical furnace. The temperature of MO$_2$ pellets with microwave heating increased quickly with input power and the variation of output power depended on the reaction characteristics of SiC and MO$_2$ with microwave. The sintered density of UO$_2$+5wt% CeO$_2$ pellets sintered in the microwave furnace was lower about 2% T.D. than that of the pellets sintered in an electrical furnace with sintering parameters. The microstructure of pellets sintered in microwave furnace has a broader pore distribution but has a larger grain size than that of the pellets sintered in the electrical furnace.
정창용 ( Chang Young Joung ),홍진태 ( Jin Tae Hong ),김가혜 ( Ka Hye Kim ),허성호 ( Sung Ho Huh ) 대한설비관리학회 2013 대한설비관리학회지 Vol.18 No.4
A fuel test rig is fabricated by various welding technologies jointing various sensors and the end caps with cladding which inserts the nuclear fuels. To precisely weld the pin-hole which is drilled on the end cap of a nuclear fuel rod, a high-pressure filling system was designed and developed. This welding system consists of mainly a high-pressure chamber, a spot welding jig and a tungsten inert-gas (TIG) welder. The nuclear fuelrod welded with this process should not leak helium gas out of its outside, when it is taken out of the high-pressure chamber. Using this system, the performance tests were performed with TIG spot welding conditions. And the welding characteristics were conformed with welded surfaces and microstructure of end-cap samples. This paper describes not only the composition and function of the high-pressure gas filling system for filling helium gas but also methods and results of the spot welding tests.
정창용 ( Chang Yong Joung ),이철용 ( Chul Yong Lee ),홍진태 ( Jin Tae Hong ),정황영 ( Hwang Young Jeong ),안성호 ( Sung Ho Ahn ) 대한설비관리학회 2011 대한설비관리학회지 Vol.16 No.3
The MI(Mineral Insulated) cable is used for instrumentation of the nuclear fuel and material irradiation in the fuel test rig assembly due to its high electrical insulation, heat resistance and mechanical strength. During the installation of the instruments, if the MI cable is damaged by an inadvertent impact, it should be recovered with simple operation because it is difficult to change the sensors (T.C, LVDT and SPND etc.) and MI cables. In this sturdy, a new recovery method of the MI cable has been developed with several tests and verified its validity. Recovery process of the MI cable consists of removal process of the sheath of MI cable, joining process of the signal wires and recovery process of the sheath with a bushing. The validity of the proposed technique has been verified with insulation test.
Dy<sub>2</sub>O<sub>3</sub>-TiO<sub>2</sub> 산화물의 소결성 및 소결체 특성에 관한 연구
김한수,정창용,김시형,이병호,이영우,손동성,이상현,Kim, Han-Soo,Joung, Chang-Yong,Kim, Si-Hyung,Lee, Byoung-Ho,Lee, Young-Woo,Sohn, Dong-Seong,Lee, Sang-Hyun 한국세라믹학회 2002 한국세라믹학회지 Vol.39 No.11
산화물 제어봉 물질로서 $Dy_xTi_yO_z$ 소결체를 powder process에 의해 제조하였다. $Dy_2O_3+TiO_2$ 혼합분말의 소결성과 고용체의 상을 TMA와 XRD로써 각각 분석하였으며, 소결체의 비열과 열확산계수를 측정하여 열전도도를 구하였다. $Dy_xTi_yO_z$에서 Dy의 함량에 따라 소결성과 밀도가 변하였고 $3\;g\;Dy/cm^3\;Dy_xTi_yO_z$의 경우 $1580{\circ}C$의 소결온도에서 용융이 일어났다. $4.00\;g\;Dy/cm^3$ 소결체에는 $Dy_2TiO_5+Dy_2Ti_2O_7$의 두 상이 존재하며 $4.54\;g\;Dy/cm^3$의 경우 $Dy_2TiO_5$의 단일 상만이 존재하는 결과를 보였다. $Dy_xTi_yO_z$의 열전도도는 $25~600{\circ}C$ 범위에서 온도에 따라 큰 변화가 없으며 $1600{\circ}C$ 소결체가 1.69∼1.78 W/mK, 1550$^{\circ}C$ 소결체의 경우에는 1.49~1.55 W/mK이었다. .$Dy_xTi_yO_z$ pellets were fabricated as a reactor control material by the powder process. Sinterability of $Dy_2O_3+TiO_2$ mixtures and phases of solid solutions were analyzed by using TMA and XRD, respectively. The thermal conductivity of .$Dy_xTi_yO_z$ pellet was determined from the measurement data of the specific heat and the thermal diffusivity of the pellet. The sinterability and the sintered density varied as a function of Dy content in $Dy_xTi_yO_z$. The pellet of $3\;g\;Dy/cm^3\;Dy_xTi_yO_z$ melted in the sintering temperature of $1580{\circ}C$. There were two phases of $Dy_2TiO_5+Dy_2Ti_2O_7$ and a single phase of $Dy_2TiO_5$ for the pellet that has the Dy content of .$4.00\;g\;Dy/cm^3$ and .$4.54\;g\;Dy/cm^3$, respectively. The thermal conductivity of $Dy_xTi_yO_z$ was nearly constant in the temperature range of $25~600{\circ}$. It was 1.69~1.78 W/mK for the pellet sintered in .$1600{\circ}$ and 1.49~1.55 W/mK for the pellet sintered in $1550{\circ}$.
정황영 ( Hwang Young Jeong ),홍진태 ( Jin Tae Hong ),정창용 ( Chang Yong Joung ),안성호 ( Sung Ho Ahn ) 대한설비관리학회 2011 대한설비관리학회지 Vol.16 No.3
The In-Pile Test Section(IPS) installed in HANARO Fuel Test Loop(FTL) is designed as a pressure vessel design conditions of 350℃, 17.5MPa. The instrumentation MI-cables for thermocouples, SPND and LVDT are passed through the sealing plug, which is in the pressure boundary region and is a part of instrumentation feedthrough of MI-cable. In this study, the Mechanical sealing method was considered how to replace brazing method, and performance test results are introduced to the sealing plug of graphite sealant. The performance was verified through the hydrostatic test, and helium leak test.
홍진태(Jintae Hong),정창용(Chang-Young Joung),허성호(Sung-Ho Heo),김가혜(Ka-Hye Kim) 대한기계학회 2015 大韓機械學會論文集A Vol.39 No.1
핵연료 연소시험 도중 핵연료봉에서 발생하는 열을 효과적으로 제거하기 위해서는 핵연료의 발열량을 정확하게 계산하고 충분한 유속을 갖는 냉각수를 순환시켜야 한다. 하나로는 개방형 수조 형태로서 핵연료 연소시험을 위한 별도의 냉각수 순환 루프를 갖추고 있는데, 여기에 핵연료 조사리그를 장착하고 냉각수를 순환시킴으로써 조사중인 핵연료봉의 온도를 일정온도 이하로 유지시킨다. 특히 순환되는 냉각수의 유속이 매우 높은 상태에서 조사리그 내에 부착된 부품이나 센서들이 유체유발 진동에 의해 파손되거나 기능을 상실하는 경우 매우 큰 기회비용을 야기한다. 본 연구에서는 조사리그 부품의 건전성 사전 검토 및 고속 유동에서의 센서 동작 특성에 대한 사전검토를 위해 냉각수 모의 순환장치를 개발하였다. To remove heat generated during a burn-up test of nuclear fuels, the heat generation rate of nuclear fuels should be calculated accurately, and a coolant should be circulated in the test loop at an adequate flow rate. HANARO is an open pool?type reactor with an independent test loop for the burn-up test of nuclear fuels. A test rig is installed in the test loop, and a coolant is circulated through the test loop to maintain the temperature of the nuclear fuel rods within a desired temperature during an irradiation test. The components and sensors in the test rig can be broken or malfunction owing to the flow-induced vibration. In this study, a coolant flow simulation system was developed to verify and confirm the soundness of components and sensors assembled in the test rig with a high flow rate of the coolant.