http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
이명호,Lee, Myung-Ho Korean Society of Soil and Groundwater Environment 2007 지하수토양환경 Vol.12 No.3
다공질매체를 통한 미세 입자의 이동은 고함수비 오염준설토의 탈수 및 오염물질의 제거와 같은 지반의 안정화 처리 및 토양의 정화에 있어서 중요한 메커니즘이 되고 있다. 일반적으로 음전하를 갖는 미세 입자들은 동전기영동의 영향으로 양극(+)방향으로 이동하게 된다. 그러나 중금속과 같은 양전하를 띈 오염물질로 흡착된 미세 입자의 경우 중금속의 종류 및 오염도에 따라 동전기영동에 의한 움직임은 제약을 받을 수 있다. 본 연구에서는 자연상태의 미세토립자의 침강거동 및 직류전류의 영향 하에서 발생되는 동전기영동에 의한 침강 거동에 대하여 조사하였다. Contaminated sediments more than 30 million/$m^3$ is generated from dredging work for harbours and coastal maintenance in Korea. Approximately 300 million/$m^3$ of sediments is dredged to deepen harbours and shipping lanes in US and of which $3{\sim}12million/m^3$ is highly contaminated. Although much is known about technologies for the remediation of heavy metal contaminated soil, much less is known about the treatment of contaminated sediment. In general, negatively charged fine particles will migrate towards positively charged system of electrodes under the influence of electrophoresis. However, the electrically induced migration of colloidal particles contaminated with heavy metals may be hindered by the positively charged heavy metal contaminants adsorbed onto the soil surfaces depending on the contamination level. This paper demonstrates settling behaviour of clayey soil by comparison with electrophoretic particle movement under the effects of heavy metal contamination, applied electric field strength, and its polarity changed by the electrode configuration.
Zr-1.0Nb-xSn 합금의 부식거동에 대한 Sn첨가의 영향
이명호,최병권,정용환,Lee, Myeong-Ho,Choe, Byeong-Gwon,Jeong, Yong-Hwan 한국재료학회 2002 한국재료학회지 Vol.12 No.5
To investigate the corrosion behavior of Zr-1.0Nb-xSn (x=1.0, 1.5, 2.0 and 2.5wt. %)alloy system, the corrosion tests of Zr-1.0Nb-xSn alloys were carried out in steam at $400^{\circ}C$ for 125 days and in 70ppm LiOH solution at $360^{\circ}C$ for 180 days. The matrix microstructures of the test specimens were analyzed using TEM and the oxide structures on the test specimens were analyzed using XRD. It was found from the analyses that the more Sn content the alloy had, the faster it was corroded and with the increase of Sn content in the alloy the fraction of $t-ZrO_2$ to $m-ZrO_2$ was decreased. It was also found that the alloys having more Sn showed more dislocation density than those having less.
이명호,김준환,최병권,정용환,Lee M. H.,Kim J. H.,Choi B. K.,Jeong Y. H. 한국재료학회 2004 한국재료학회지 Vol.14 No.10
To study the dynamic strain aging behavior of Zr-0.4Sn-1.5Nb-0.2Fe sample tube for nuclear fuel cladding in the range of pressurized water reactor (PWR) operation temperature, the tensile tests of the tube specimens, which had been finally heat-treated at $470^{\circ}C\;and\;510^{\circ}C$, had been carried out with the strain rate $1.67{\times}10^{-2}/s\;and\;8.33{\times}10^{-5}/s$ at the various temperatures from room temperature to $500^{\circ}C$. It was observed that the elongation of the specimens got shortened as the temperature increased from $200^{\circ}C\;to\;340^{\circ}C$. The specimens that were finally heat-treated at $470^{\circ}C$ showed a plateau more remarkably on the plot of yield strength-temperature than those heat-treated at $510^{\circ}C$. In the range of $310\sim400^{\circ}C$, the strain rate sensitivity of the specimens finally heat-treated at $510^{\circ}C$ was $30.4\%\sim33.7\%$ lower but the work hardening exponent index of the specimens was a little higher than that without dynamic strain aging effect.