Corrosion behavior of dispersion-strengthened ferritic Fe-13Cr-2Mo steel in lead melt
作者： O. I. Eliseeva , V. P. Tsisar , I. I. Ivanova , A. M. Demidik
DOI: 10.1007/S11106-008-9063-X
关键词:
摘要: The corrosion behavior of dispersion-strengthened ferritic Fe-13Cr-2Mo (TiO2) steel in oxygen-containing lead melt is investigated at 550 and 650°C. It determined that duplex magnetite scale formed on the surface 550°C oxygen concentration about 10−3 wt.% melt. grows symmetrically with regard to initial steel-melt interface toward liquid metal matrix. outer oxide layer consists Fe3O4, upper part which contains plumboferrites, while inner Cr-rich spinel Fe1+xCr2−xO4. As grows, imperfection increases. oxidation intensifies as interaction temperature increases loses its protective properties becomes penetrable for lead. With decreasing (10−5 wt.%), growth slower resistance
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sci-hub.se 参考文章(13)
Ronald G. Ballinger, Jeongyoun Lim, An Overview of Corrosion Issues for the Design and Operation of High-Temperature Lead- and Lead-Bismuth-Cooled Reactor Systems Nuclear Technology. ,vol. 147, pp. 418- 435 ,(2004) , 10.13182/NT04-A3540
G Müller, A Heinzel, J Konys, G Schumacher, A Weisenburger, F Zimmermann, V Engelko, A Rusanov, V Markov, Results of steel corrosion tests in flowing liquid Pb/Bi at 420-600 °C after 2000 h Journal of Nuclear Materials. ,vol. 301, pp. 40- 46 ,(2002) , 10.1016/S0022-3115(01)00725-5
D. Gómez Briceño, L. Soler Crespo, F.J. Martı́n Muñoz, F. Hernández Arroyo, Influence of temperature on the oxidation/corrosion process of F82Hmod. martensitic steel in lead–bismuth Journal of Nuclear Materials. ,vol. 303, pp. 137- 146 ,(2002) , 10.1016/S0022-3115(02)00817-6
Shigeharu Ukai, Masayuki Fujiwara, Perspective of ODS alloys application in nuclear environments Journal of Nuclear Materials. ,vol. 307-311, pp. 749- 757 ,(2002) , 10.1016/S0022-3115(02)01043-7
Masatoshi KONDO, Minoru TAKAHASHI, Naoki SAWADA, Koji HATA, Corrosion of Steels in Lead–Bismuth Flow Journal of Nuclear Science and Technology. ,vol. 43, pp. 107- 116 ,(2006) , 10.1080/18811248.2006.9711073
F Barbier, A Rusanov, Corrosion behavior of steels in flowing lead–bismuth Journal of Nuclear Materials. ,vol. 296, pp. 231- 236 ,(2001) , 10.1016/S0022-3115(01)00521-9
Y. Kurata, M. Futakawa, S. Saito, Comparison of the corrosion behavior of austenitic and ferritic/martensitic steels exposed to static liquid Pb-Bi at 450 and 550 °C Journal of Nuclear Materials. ,vol. 343, pp. 333- 340 ,(2005) , 10.1016/J.JNUCMAT.2004.07.064
R.L. Klueh, D.S. Gelles, S. Jitsukawa, A. Kimura, G.R. Odette, B. van der Schaaf, M. Victoria, Ferritic/martensitic steels – overview of recent results Journal of Nuclear Materials. ,vol. 307-311, pp. 455- 465 ,(2002) , 10.1016/S0022-3115(02)01082-6
Jinsuo Zhang, Ning Li, Yitung Chen, A.E. Rusanov, Corrosion Behaviors of US Steels in Flowing Lead-Bismuth Eutectic (LBE) Journal of Nuclear Materials. ,vol. 336, pp. 1- 10 ,(2005) , 10.1016/J.JNUCMAT.2004.08.002
Allen L Johnson, Denise Parsons, Julia Manzerova, Dale L Perry, Dan Koury, Brian Hosterman, John W Farley, Spectroscopic and microscopic investigation of the corrosion of 316/316L stainless steel by lead–bismuth eutectic (LBE) at elevated temperatures: importance of surface preparation Journal of Nuclear Materials. ,vol. 328, pp. 88- 96 ,(2004) , 10.1016/J.JNUCMAT.2004.03.006