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NTIS 바로가기Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.41 no.1, 2009년, pp.107 - 112
Zhang, Qiang (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China) , Tang, Rui (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China) , Li, Cong (China Nuclear Power Technology Research Institute) , Luo, Xin (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China) , Long, Chongsheng (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China) , Yin, Kaiju (National Key Lab. For Nuclear Fuel and Materials, Nuclear Power Institute of China)
Corrosion of nickel-base alloys (Hastelloy C-276, Inconel 625, and Inconel X-750) in
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T.C. Totemeier, D.E. Clark. Effect of transient thermal cycles in a supercritical water-cooled reactor on the microstructure and properties of ferritic-martensitic steels. Journal of Nuclear Materials, 2006, 355: 104
D.R. Novog, J. Luxat, L.K.H. Leung. Estimation of conceptual supercritical water reactor response to a small loss of coolant accident. 3rd Int. symposium on SCWRDesign and Technology, 2007: 108-117
Y. Chen, K. Sridharan, T. Allen. Corrosion behavior of ferritic-martensitic steel T91 in supercritical water. Corrosion Science, 2006, 48 (9): 2843-2854
L. Tan, Y. Yang, T. R. Allen. Oxidation behavior of ironbased alloy HCM12A exposed in supercritical water. Corrosion Science, 2006, 48 (10): 3123-2138
Yongsun Yi, Byeonghak Lee, Sungho Kim, et al. Corrosion and corrosion fatigue behaviors of 9cr steel in a supercritical water condition. Materials Science and Engineering A, 2006, 429: 161?168
X. Gao, X. Wu, Z. Zhang, et al. Characterization of oxide films grown on 316L stainless steel exposed to H2O2- containing supercritical water. Journal of Supercritical Fluids, 2007, 42: 157-163
X. Ren, K. Sridharan, T.R. Allen. Corrosion of ferriticmartensitic steel HT9 in supercritical water. Journal of Nuclear Materials, 2006, 358: 227-234
L. Tan, M.T. Machut, K. Sridharan, et al. Corrosion behavior of a ferritic/ martensitic steel HCM12A exposed to harsh environments. Journal of Nuclear Materials, 2007, 371: 161-170
Pantip Ampornrat, Gary S. Was Oxidation of ferriticmartensitic alloys T91, HCM12A and HT-9 in supercritical water. Journal of Nuclear Materials, 2007, 371: 1-17
B.P. Somerday, K.T. Wiggans, R.W. Bradshaw. Environmentassisted failure of alloy C-276 burst disks in a batch supercritical water oxidation reactor. Engineering Failure Analysis, 2006, 13: 80-95
S.E. Ziemniak, M. Hanson. Corrosion behavior of NiCrMo Alloy 625 in high temperature, hydrogenated water. Corrosion Science, 2003, 45: 1595-1618
S.E. Ziemniak, M. Hanson. Corrosion behavior of NiCrFe Alloy 600 in high temperature, hydrogenated water. Corrosion Science, 2006, 48: 498-521
L. Tan, K. Sridharan, T. R. Allen. The effect of grain boundary engineering on the oxidation behavior of INCOLOY alloy 800H in supercritical water. Journal of Nuclear Materials, 2006, 348: 263-271
G.S. Was, P. Ampornrat, G. Gupta, et al. Corrosion and stress corrosion cracking in supercritical water. Journal of Nuclear Materials, 2007, 371: 176-201
D. Rats, L. Vandenbulcke, R. Herbin, R. Benoit, R. Erre, V. Serin, J. Sevely, Thin Solid Films 270 (1995) 177
G. Latha, N. Rajendran, S. Rajeswari, J. Mater. Eng. Perform. 6 (1997) 743
H.C. Brookes, J.W. Bayles, F.J. Graham, J. Appl. Electrochem. 20 (1990) 223
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