Journal of Shanghai Jiaotong University ›› 2016, Vol. 50 ›› Issue (04): 528-533.
Previous Articles Next Articles
LU Hui,SHEN Zhao,ZHANG Lefu
Received:
2015-03-12
Online:
2016-04-28
Published:
2016-04-28
CLC Number:
LU Hui,SHEN Zhao,ZHANG Lefu. Formation Mechanism and Properties of Oxide Film on 310-ODS Steel in Supercritical Water[J]. Journal of Shanghai Jiaotong University, 2016, 50(04): 528-533.
[1]ZHANG L, BAO Y, TANG R. Selection and corrosion evaluation tests of candidate SCWR fuel cladding materials[J]. Nuclear Engineering and Design,2012,249(8): 180187. [2]UKAI S, HARADA M, OKADA H, et al. Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials[J]. Journal of Nuclear Materials, 1993, 204(9): 6573. [3]UKAI S, NISHIDA T, OKADA H, et al. Development of oxide dispersion strengthened ferritic steels for FBR core application,(I) improvement of mechanical properties by recrystallization processing[J]. Journal of Nuclear Science and Technology, 1997, 34(3): 256263. [4]MONNET I, DUBUISSON P, SERRUYS Y, et al. Microstructural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels[J]. Journal of Nuclear Materials, 2004,335(3): 311321. [5]邹雷, 周张健, 孙红英, 等. ODS310 合金的高温氧化行为[J]. 北京科技大学学报, 2014,36(9):11951200. ZOU Lei, ZHOU Zhangjian, SUN Hongying, et al. High temperature oxidation behavior of ODS310 alloy[J]. Journal of University of Science and Technology Beijing, 2014, 36(9): 11951200. [6]WAS G S, AMPORNRAT P, GUPTA G, et al. Corrosion and stress corrosion cracking in supercritical water[J]. Journal of Nuclear Materials, 2007, 371(1): 176201. [7]WAS G S, TEYSSEYRE S, JIAO Z. Corrosion of austenitic alloys in supercritical water[J]. Corrosion,2006, 62(11): 9891005. [8]BOYD W K, PRAY H A. Corrosion of stainless steels in supercritical water[J]. Corrosion, 1957,13(6): 3342. [9]ROBERTSON J. The mechanism of high temperature aqueous corrosion of steel[J]. Corrosion Science,1989, 29(11): 12751291. [10]SUN M, WU X, ZHANG Z, et al. Analyses of oxide films grown on alloy 625 in oxidizing supercritical water[J]. The Journal of Supercritical Fluids, 2008, 47(2): 309317. [11]SUN M, WU X, ZHANG Z, et al. Oxidation of 316 stainless steel in supercritical water[J]. Corrosion science, 2009, 51(5): 10691072. [12]ATKINSON A. Transport processes during the growth of oxide films at elevated temperature[J]. Reviews of Modern Physics, 1985, 57(2): 437. [13]AMPORNRAT P, WAS G S. Oxidation of ferriticmartensitic alloys T91, HCM12A and HT9 in supercritical water[J]. Journal of Nuclear Materials, 2007, 371(1): 117. [14]HU H L, ZHOU Z J, LIAO L, et al. Corrosion behavior of a 14CrODS steel in supercritical water[J]. Journal of Nuclear Materials, 2013, 437(1):196200. [15]HU H, ZHOU Z, LI M, et al. Study of the corrosion behavior of a 18Croxide dispersion strengthened steel in supercritical water[J]. Corrosion Science,2012, 65(12): 209213 |
[1] | WANG Jiamei1,DUAN Zhengang1,ZHANG Lefu1,MENG Fanjiang2,SHI Xiuqiang2. Electrochemical Corrosion Behaviors of Alloy 690 in High-Temperature and Highpressure Water [J]. Journal of Shanghai Jiaotong University, 2016, 50(04): 514-520. |
[2] | CHEN Kai,DU Donghai,ZHANG Lefu. Corrosion Fatigue Crack Growth Behavior of Alloy 690 in PressurizedWater Reactor Environment [J]. Journal of Shanghai Jiao Tong University, 2017, 51(11): 1281-1286. |
[3] | WANG Jiamei1,SU Haozhan1,HE Kun2,ZHANG Lefu1. Effects of Potential on 508III-52M-690 Dissimilar Weld Joint [J]. Journal of Shanghai Jiao Tong University, 2018, 52(4): 447-454. |
[4] | CHEN Kai 1,DU Donghai1,LU Hui1,ZHANG Lefu1,SHI Xiuqiang2,XU Xuelian2. Fatigue Crack Growth of Alloy 690 Tubing [J]. Journal of Shanghai Jiaotong University, 2014, 48(11): 1639-1643. |
[5] | DU Donghai1,LU Hui1,CHEN Kai1,ZHANG Lefu1,SHI Xiuqiang2,XU Xuelian2. SCC Crack Growth Rate Dependence of Cold Worked 316L Stainless Steel on Dissolved Oxygen in High Temperature Water [J]. Journal of Shanghai Jiaotong University, 2014, 48(11): 1644-1649. |
Viewed | ||||||
Full text |
|
|||||
Abstract |
|
|||||