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Browse "NE-Journal Papers(저널논문)" by Subject ENVIRONMENTS

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Showing results 1 to 8 of 8

1	Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors Kim, Hyunmyung; Jang, Hun; Subramanian, Gokul Obulan; Kim, Chaewon; Jang, Changheui, JOURNAL OF NUCLEAR MATERIALS, v.507, pp.1 - 14, 2018-08
2	Development of an aluminide coating layer on Alloy 617 by Al sputtering and inter-diffusion heat treatments Kim, Dong-Hoon; Sah, Injin; Lee, Ho Jung; Hong, Sunghoon; Jang, Changheui, SURFACE & COATINGS TECHNOLOGY, v.244, pp.15 - 22, 2014-04
3	Fatigue life and crack growth mechanisms of the type 316LN austenitic Stainless Steel in 310 degrees C deoxygenated water Cho, Hyunchul; Kim, Byoung Koo; Kim, In Sup; Jang, Changheui; Jung, Dae Yul, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.44, no.7, pp.1007 - 1014, 2007-07
4	Influence of microstructure on hydrothermal corrosion of chemically vapor processed SiC composite tubes Kim, Daejong; Lee, Ho Jung; Jang, Changheui; Lee, Hyeon-Geun; Park, Ji Yeon; Kim, Weon-Ju, JOURNAL OF NUCLEAR MATERIALS, v.492, pp.6 - 13, 2017-08
5	Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310 degrees C deaerated water-fatigue life and dislocation structure development Cho, Hyunchul; Kim, Byoung Koo; Kim, In Sup; Jang, Changheui, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.476, no.1-2, pp.248 - 256, 2008-03
6	Mechanical analysis of surface-coated zircaloy cladding Lee, Youho; Lee, Jeong-Ik; No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.49, no.5, pp.1031 - 1043, 2017-08
7	Microstructure evolution of a Ni-Cr-W superalloy during long-term aging at high temperatures Lee, Ho Jung; Kim, Hyunmyung; Kim, Donghoon; Jang, Changheui, MATERIALS CHARACTERIZATION, v.106, pp.283 - 291, 2015-08
8	Novel Roaming and Stationary Tethered Aerial Robots for Continuous Mobile Missions in Nuclear Power Plants Gu, Beom Woo; Choi, Su Yong; Choi, Young Soo; Cai, Guowei; Seneviratne, Lakmal; Rim, Chun Taek, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.4, pp.982 - 996, 2016-08

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