Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions
暂无分享,去创建一个
[1] Y. Katoh,et al. Swelling of nuclear graphite and high quality carbon fiber composite under very high irradiation temperature , 2008 .
[2] Sven Ulrich,et al. Raman spectroscopy on amorphous carbon films , 1996 .
[3] T. Hinoki,et al. Effect of irradiation damage on hydrothermal corrosion of SiC , 2015 .
[4] Lance Lewis Snead,et al. Evaluation of neutron irradiated silicon carbide and silicon carbide composites , 2007 .
[5] Y. Katoh,et al. Handbook of SiC properties for fuel performance modeling , 2007 .
[6] P. May,et al. High temperature properties of SiC and diamond CVD-monofilaments , 2005 .
[7] J. Robertson,et al. Interpretation of Raman spectra of disordered and amorphous carbon , 2000 .
[8] J. Kaae. The Mechanical Behavior of Biso-Coated Fuel Particles during Irradiation. Part I: Analysis of Stresses and Strains Generated in the Coating of a Biso Fuel Particle during Irradiation , 1977 .
[9] William J. Weber,et al. Displacement damage in silicon carbide irradiated in fission reactors , 2004 .
[10] Daejong Kim,et al. Fabrication and measurement of hoop strength of SiC triplex tube for nuclear fuel cladding applications , 2015 .
[11] A. Kelly,et al. Theory of multiple fracture of fibrous composites , 1973 .
[12] Kurt A. Terrani,et al. Silicon Carbide Oxidation in Steam up to 2 MPa , 2014 .
[13] Y. Katoh,et al. Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature , 2016 .
[14] Akira Hasegawa,et al. Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects , 2014 .
[15] C. Back,et al. Characterization of SiC–SiC composites for accident tolerant fuel cladding , 2015 .
[16] M. Tamor,et al. Raman ``fingerprinting'' of amorphous carbon films , 1994 .
[17] Lance Lewis Snead,et al. Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures , 2010 .
[18] Lance Lewis Snead,et al. High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties , 2015 .
[19] J. Lamon,et al. Analysis of crack deviation in ceramic matrix composites and multilayers based on the Cook and Gordon mechanism , 2007 .
[20] P. Pirouz,et al. The microstructure of SCS-6 SiC fiber , 1991 .
[21] C. Sauder. Ceramic Matrix Composites: Nuclear Applications , 2014 .
[22] Yutai Katoh,et al. Current status and recent research achievements in SiC/SiC composites , 2014 .
[23] Steven J. Zinkle,et al. Materials Challenges in Nuclear Energy , 2013 .
[24] Frank W. Zok,et al. The physics and mechanics of fibre-reinforced brittle matrix composites , 1994, Journal of Materials Science.
[25] E. Rohmer,et al. Mechanical properties of SiC/SiC braided tubes for fuel cladding , 2014 .
[26] William A. Curtin,et al. THEORY OF MECHANICAL-PROPERTIES OF CERAMIC-MATRIX COMPOSITES , 1991 .
[27] M. Kazimi,et al. Characteristics of Composite Silicon Carbide Fuel Cladding after Irradiation under Simulated PWR Conditions , 2013 .
[28] A. Mitsuishi,et al. Characterization of the free‐carrier concentrations in doped β‐SiC crystals by Raman scattering , 1987 .
[29] Lance Lewis Snead,et al. High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations , 2015 .
[30] B. Sammuli,et al. Fabrication of SiC–SiC composites for fuel cladding in advanced reactor designs , 2012 .
[31] C. Sauder,et al. Anisotropic damage behavior of SiC/SiC composite tubes: Multiaxial testing and damage characterization , 2015 .