Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications

被引:77
作者
Pint, B. A. [1 ]
Dryepondt, S. [1 ]
Unocic, K. A. [1 ]
Hoelzer, D. T. [1 ]
机构
[1] Oak Ridge Natl Lab, Div Mat Sci & Technol, Oak Ridge, TN 37831 USA
关键词
HIGH-TEMPERATURE OXIDATION; CLADDING CANDIDATE MATERIALS; ALUMINA SCALE FORMATION; MECHANICAL-PROPERTIES; ALLOYS; STEEL; ADDITIONS; GROWTH; STEAM; SEGREGATION;
D O I
10.1007/s11837-014-1200-z
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Oxide dispersion strengthened (ODS) FeCrAl alloys with 12-15% Cr are being evaluated for improved compatibility with Pb-Li for a fusion energy application and with high temperature steam for a more accident-tolerant light water reactor fuel cladding application. A 12% Cr content alloy showed low mass losses in static Pb-Li at 700 degrees C, where a LiAlO2 surface oxide formed and inhibited dissolution into the liquid metal. All the evaluated compositions formed a protective scale in steam at 1200 degrees C, which is not possible with ODS FeCr alloys. However, most of the compositions were not protective at 1400 degrees C, which is a general and somewhat surprising problem with ODS FeCrAl alloys that is still being studied. More work is needed to optimize the alloy composition, microstructure and oxide dispersion, but initial promising tensile and creep results have been obtained with mixed oxide additions, i.e. Y2O3 with ZrO2, HfO2 or TiO2.
引用
收藏
页码:2458 / 2466
页数:9
相关论文
共 55 条
[1]   The influence of the moisture content of the atmosphere on alumina scale formation and growth during high temperature oxidation of PM2000 [J].
Al-Badairy, H ;
Tatlock, GJ .
MATERIALS AT HIGH TEMPERATURES, 2000, 17 (01) :133-137
[2]  
BENNETT MJ, 1991, HEAT RESISTANT MATERIALS, P95
[3]   Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure [J].
Cheng, Ting ;
Keiser, James R. ;
Brady, Michael P. ;
Terrani, Kurt A. ;
Pint, Bruce A. .
JOURNAL OF NUCLEAR MATERIALS, 2012, 427 (1-3) :396-400
[4]   TEM and HRTEM study of oxide particles in an Al-alloyed high-Cr oxide dispersion strengthened steel with Zr addition [J].
Dou, Peng ;
Kimura, Akihiko ;
Kasada, Ryuta ;
Okuda, Takanari ;
Inoue, Masaki ;
Ukai, Shigeharu ;
Ohnuki, Somei ;
Fujisawa, Toshiharu ;
Abe, Fujio .
JOURNAL OF NUCLEAR MATERIALS, 2014, 444 (1-3) :441-453
[5]   Effects of extrusion temperature on the nano-mesoscopic structure and mechanical properties of an Al-alloyed high-Cr ODS ferritic steel [J].
Dou, Peng ;
Kimura, Akihiko ;
Okuda, Takanari ;
Inoue, Masaki ;
Ukai, Shigeharu ;
Ohnuki, Somei ;
Fujisawa, Toshiharu ;
Abe, Fujio .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :166-170
[6]  
Field K.G., 2014, STABILITY FECRAL ALL
[7]   INFLUENCE OF YTTRIUM ADDITIONS ON OXIDE-SCALE ADHESION TO AN IRON-CHROMIUM-ALUMINUM ALLOY [J].
GOLIGHTLY, FA ;
STOTT, FH ;
WOOD, GC .
OXIDATION OF METALS, 1976, 10 (03) :163-187
[8]   MICROSTRUCTURE, ADHESION AND GROWTH-KINETICS OF PROTECTIVE SCALES ON METALS AND ALLOYS [J].
HINDAM, H ;
WHITTLE, DP .
OXIDATION OF METALS, 1982, 18 (5-6) :245-284
[9]  
Hoelzer D.T., 2014, DEV ODS FECRAL FERRI
[10]   Development of Al added high-Cr ODS steels for fuel cladding of next generation nuclear systems [J].
Kimura, A. ;
Kasada, R. ;
Iwata, N. ;
Kishimoto, H. ;
Zhang, C. H. ;
Isselin, J. ;
Dou, P. ;
Lee, J. H. ;
Muthukumar, N. ;
Okuda, T. ;
Inoue, M. ;
Ukai, S. ;
Ohnuki, S. ;
Fujisawa, T. ;
Abe, T. F. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :176-179