High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties

Abstract Nuclear-grade silicon carbide (SiC) composite material was examined for mechanical and thermophysical properties following high-dose neutron irradiation in the High Flux Isotope Reactor at a temperature range of 573–1073 K. The material was chemical vapor-infiltrated SiC-matrix composite with a two-dimensional satin weave Hi-Nicalon Type S SiC fiber reinforcement and a multilayered pyrocarbon/SiC interphase. Moderate (1073 K) to very severe (573 K) degradation in mechanical properties was found after irradiation to >70 dpa, whereas no evidence was found for progressive evolution in swelling and thermal conductivity. The swelling was found to recover upon annealing beyond the irradiation temperature, indicating the irradiation temperature, but only to a limited extent. The observed strength degradation is attributed primarily to fiber damage for all irradiation temperatures, particularly a combination of severe fiber degradation and likely interphase damage at relatively low irradiation temperatures.

[1]  M. Ferraris,et al.  Silicon carbide composites as fusion power reactor structural materials , 2011 .

[2]  Lance Lewis Snead,et al.  Revisiting the Use of SiC as a Post Irradiation Temperature Monitor , 2004 .

[3]  Mark S. Tillack,et al.  Design and material issues for high performance SiCf/SiC-based fusion power cores , 2001 .

[4]  Lance Lewis Snead,et al.  High dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites, Part 1: Microstructural evaluations , 2015 .

[5]  A. Kohyama,et al.  SiC/SiC composites through transient eutectic-phase route for fusion applications , 2004 .

[6]  Y. Katoh,et al.  Stability of SiC and its composites at high neutron fluence , 2011 .

[7]  C. Sauder Ceramic Matrix Composites: Nuclear Applications , 2014 .

[8]  Akira Kohyama,et al.  The effect of high dose/high temperature irradiation on high purity fibers and their silicon carbide composites , 2002 .

[9]  Toyohiko Yano,et al.  X-ray diffractometry and high-resolution electron microscopy of neutron-irradiated SiC to a fluence of 1.9×1027 n/m2 , 1998 .

[10]  S. Zinkle,et al.  Measurement of the effect of radiation damage to ceramic composite interfacial strength , 1992 .

[11]  Y. Katoh,et al.  Handbook of SiC properties for fuel performance modeling , 2007 .

[12]  K. Terrani,et al.  Silicon carbide composite for light water reactor fuel assembly applications , 2014 .

[13]  William A. Curtin,et al.  THEORY OF MECHANICAL-PROPERTIES OF CERAMIC-MATRIX COMPOSITES , 1991 .

[14]  Yutai Katoh,et al.  Effects of neutron irradiation on mechanical properties of silicon carbide composites fabricated by nano-infiltration and transient eutectic-phase process , 2014 .

[15]  R. Naslain Design, preparation and properties of non-oxide CMCs for application in engines and nuclear reactors: an overview , 2004 .

[16]  Akira Hasegawa,et al.  Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects , 2014 .

[17]  Y. Katoh,et al.  Mechanical properties of advanced SiC fiber composites irradiated at very high temperatures , 2011 .

[18]  J. Hegeman,et al.  Mechanical and thermal properties of SiCf/SiC composites irradiated with neutrons at high temperatures , 2005 .

[19]  R. Price ANNEALING BEHAVIOR OF NEUTRON-IRRADIATED SILICON CARBIDE TEMPERATURE MONITORS. , 1972 .

[20]  J. E. Palentine The calibration of fast reactor irradiated silicon carbide temperature monitors using a length measurement technique , 1980 .

[21]  A. Bunsell,et al.  A review of the development of three generations of small diameter silicon carbide fibres , 2006 .

[22]  Lance Lewis Snead,et al.  Evaluation of neutron irradiated silicon carbide and silicon carbide composites , 2007 .

[23]  Akira Kohyama,et al.  Mechanical properties of advanced SiC/SiC composites after neutron irradiation , 2007 .

[24]  K. Ozawa,et al.  Irradiation-induced shrinkage of highly crystalline SiC fibers , 2015 .

[25]  W. J. Weber,et al.  Radiation effects in SiC for nuclear structural applications , 2012 .

[26]  S. Zinkle,et al.  Thermal conductivity degradation of ceramic materials due to low temperature, low dose neutron irradiation , 2005 .

[27]  R. J. Price,et al.  Properties of silicon carbide for nuclear fuel particle coatings , 1977 .

[28]  Aljaž Iveković,et al.  Current status and prospects of SiCf/SiC for fusion structural applications , 2013 .

[29]  Lance Lewis Snead,et al.  Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures , 2010 .

[30]  Anthony G. Evans,et al.  Methodology for Relating the Tensile Constitutive Behavior of Ceramic‐Matrix Composites to Constituent Properties , 1994 .

[31]  Y. Katoh,et al.  Effect of neutron irradiation on tensile properties of unidirectional silicon carbide composites , 2007 .

[32]  Akira Kohyama,et al.  Evaluation of neutron irradiated near-stoichiometric silicon carbide fiber composites , 2000 .