• 소성∙가공
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• 제21권1호
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• pp.13-18
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• 2012

During warm forging, materials are formed in the temperature range of $300^{\circ}C\sim900^{\circ}C$. In this temperature range, the friction between the forging die and the material is very high and has a negative effect on the forming process causing severe die wear and possible defects in the component because of stick-slip. Thus, lubrication characteristics are a very important factor for productivity during warm forging. In this paper, ring compression experiments were conducted to estimate the friction factor between the die and the materials as the main factor in characterizing the lubricant. Also, ring tests using normal graphite power as a lubricant coating system were compared with tests using nano graphite powder. The results confirm that the nano graphite is superior to the normal graphite in view of its lubricating effect. In addition, the friction factor (m) was estimated with respect to the amount of the nano graphite content in the lubricant. With 10 % nano graphite the friction factor had the lowest value as compared to other amounts. It can be concluded that the amount of the nano graphite in the coating system can be optimized to obtain the best lubrication condition between the die and the material using ring test experiments.

• 에너지공학
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• 제22권2호
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• pp.237-244
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• 2013

엔진오일은 다양한 내연기관의 윤활을 위한 가장 기본적인 윤활제이다. 최근 자동차사 및 엔진오일 제조사 등은 엔진오일의 교환주기를 15000~20000 km를 권장하고 있는 반면, 대부분의 정비관련업자 및 운전자들은 엔진오일의 성능진보와는 별개로 관습적으로 매5000 km 마다 엔진오일을 교환권유 또는 인식하고 있다. 빈번한 엔진오일의 교환은 폐엔진오일로 인한 환경오염과 차량 유지비 등의 증가요인으로 대두되고 있다. 따라서 본 연구에서는 신유와 실제 운행조건의 차량을 활용하여 5000 km, 10000 km를 각각 주행한 후 회수된 사용엔진오일의 다양한 물성으로 인화점, 유동점, 동점도, 저온겉보기점도, 전산가, 4구식 내마모시험 및 금속분을 조사 분석하였다. 결과적으로 사용엔진오일은 신유에 비해 전산가, 마모흔, 철과 구리 성분 증가가 다소 관찰되었지만, 주행거리별 사용엔진오일의 물성 및 금속분 변화는 거의 유사하였다.

• Nuclear Engineering and Technology
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• 제50권2호
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• pp.223-228
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• 2018

AREVA NP (Courbevoie, Paris, France) is actively developing several enhanced accident-tolerant fuels cladding concepts ranging from near-term evolutionary (Cr-coated zirconium alloy cladding) to long-term revolutionary (SiC/SiC composite cladding) solutions, relying on its worldwide teams and partnerships, with programs and irradiations planned both in Europe and the United States. The most advanced and mature solution is a dense, adherent chromium coating on zirconium alloy cladding, which was initially developed along with the CEA and EDF in the French joint nuclear R&D program. The evaluation of the out-of-pile behavior of the Cr-coated cladding showed excellent results, suggesting enhanced reliability, enhanced operational flexibility, and improved economics in normal operating conditions. For example, because chromium is harder than zirconium, the Cr coating provides the cladding with a significantly improved wear resistance. Furthermore, Cr-coated samples exhibit extremely low corrosion kinetics in autoclave and prevents accelerated corrosion in harsh environments such as in water with 70 ppm Li leading to improved operational flexibility. Finally, AREVA NP has fabricated a physical vapor deposition prototype machine to coat full-length cladding tubes. This machine will be used for the manufacturing of full-length lead test rods in commercial reactors by 2019.