Present limits and improvements of structural materials for fusion reactors – a review
暂无分享,去创建一个
[1] Steven J. Zinkle,et al. Research and development on vanadium alloys for fusion applications , 1998 .
[2] David S. Gelles,et al. Development of oxide dispersion strengthened ferritic steels for fusion , 1996 .
[3] V. Kazakov,et al. Radiation embrittlement of low-alloyed Mo alloys , 1996 .
[4] L. Snead,et al. Neutron irradiation effects on the density, tensile properties and microstructural changes in Hi-Nicalon™ and Sylramic™ SiC fibers , 1998 .
[5] G. W. Hollenberg,et al. The effect of irradiation on the stability and properties of monolithic silicon carbide and SiCf/SiC composites up to 25 dpa , 1995 .
[6] G. Pons,et al. Microstructure and Textures of Ods Ferritic Alloys Obtained by Mechanical Alloying , 1992 .
[7] David L. Smith,et al. Vanadium-base alloys for fusion first-wall/blanket applications , 2000 .
[8] R. Blackstone,et al. The expansion of silicon carbide by neutron irradiation at high temperature , 1971 .
[9] E. Lara‐Curzio. 4.18 – Properties of CVI–SiC Matrix Composites , 2000 .
[10] Karren L. More,et al. Low dose irradiation performance of SiC interphase SiC/SiC composites , 1998 .
[11] M. L. Hamilton,et al. Irradiation-enhanced creep in SiC: data summary and planned experiments , 1998 .
[12] J. W. Wilson,et al. Behaviour and Properties of Refractory Metals , 1965 .
[13] S. Zinkle,et al. Operating temperature windows for fusion reactor structural materials , 2000 .
[14] A. Hartmaier,et al. Controlling factors for the brittle-to-ductile transition in tungsten single crystals , 1998, Science.
[15] Zhiyong Zhu,et al. Dimensional changes of Al2O3 and SiC, proton irradiated under tensile stress , 1994 .
[16] Manabu Satou,et al. Tensile behavior of helium charged VTiCrSi type alloys , 1996 .
[17] S. Fabritsiev,et al. The effect of rhenium on the radiation damage resistivity of Mo–Re alloys , 1998 .
[18] R. J. Price,et al. Properties of silicon carbide for nuclear fuel particle coatings , 1977 .
[19] T. Okuda,et al. Tube manufacturing and characterization of oxide dispersion strengthened ferritic steels , 2000 .
[20] Steven J. Zinkle,et al. Amorphization of SiC under ion and neutron irradiation , 1998 .
[21] E. I. Uskov,et al. Methodological aspects of studying the fracture toughness of tungsten. Report No. 2 , 1984 .
[22] M. Seki. ITER and beyond , 1999 .
[23] R. Jones,et al. OXIDATION RESISTANT CERAMIC MATRIX COMPOSITES , 1997 .
[24] Ken C. Liu. High temperature fatigue behavior of unirradiated V-15Cr-5Ti tested in vacuum , 1981 .
[25] J. Steichen. Tensile properties of neutron irradiated TZM and tungsten , 1976 .
[26] L. Giancarli,et al. Modeling of mechanical behavior and design criteria for SiCf/SiC composite structures in fusion reactors , 2003 .
[27] M. Grossbeck,et al. Fatigue and crack growth behavior of VCrTi alloys , 1996 .
[28] Richard F. Mattas,et al. Performance limits for fusion first-wall structural materials , 1999 .
[29] E. V. Osch,et al. Irradiation testing of 316L(N)-IG austenitic stainless steel for ITER , 1998 .
[30] A. Hasegawa,et al. Neutron irradiation embrittlement of molybdenum rhenium alloys and their improvement by heat treatment , 1998 .
[31] Akira Kohyama,et al. Status of silicon carbide composites for fusion , 1996 .
[32] K. Ichikawa,et al. Effect of rhenium addition on fracture toughness of tungsten at elevated temperatures , 1995, Journal of Materials Science.
[33] F. Touboul,et al. Austenitic stainless steels, status of the properties database and design rule development , 1996 .