The effect of irradiation on the stability and properties of monolithic silicon carbide and SiCf/SiC composites up to 25 dpa

Hollenberg, G.W.; Henager, Charles H.; Youngblood, G.E.; Trimble, Daniel; Simonson, S.A.; Newsome, G.A.; Lewis, Eluned

doi:10.1016/0022-3115(94)00391-2

Cited by 87 publications

(32 citation statements)

References 16 publications

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“…[3][4][5] However, as improved SiC fibers became available, experiments started to demonstrate good tolerance of SiC/ SiC composites to neutron irradiation. [5][6][7] Those SiC fibers, which consist primarily of a polycrystalline form of cubic SiC and are termed Generation-III SiC fibers, 8) are now commercially available as Hi-NicalonÔ Type-S (Nippon Carbon Co., Tokyo, Japan) 9) and TyrannoÔ-SA (Ube Industries, Ltd., Ube, Japan).…”

Section: Introductionmentioning

confidence: 99%

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

et al. 2005

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Fast fracture properties of chemically vapor-infiltrated silicon carbide matrix composites with Hi-NicalonÔ Type-S near-stoichiometric silicon carbide fiber reinforcements and thin pyrolytic carbon interphase were studied. The primary emphasis was on preliminary assessment of the applicability of a very thin pyrolytic carbon interphase between fibers and matrices of silicon carbide composites for use in nuclear environments. It appears that the mechanical properties of the present composite system are not subject to strong interphase thickness effects, in contrast to those in conventional non-stoichiometric silicon carbide-based fiber composites. The interphase thickness effects are discussed from the viewpoints of residual thermal stress, fiber damage, and interfacial friction. A preliminary conclusion is that a thin pyrolytic carbon interphase is beneficial for fast fracture properties of stoichiometric silicon carbide composites.

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Section: Introductionmentioning

confidence: 99%

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

et al. 2005

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“…6) This is attributed primarily to shrinkage in the SiC-based fibers due to irradiation-assisted oxidation, 7) irradiation-induced recrystallization of microcrystalline fibers, 8,9) and to dimensional changes of carbon 10) interphase applied to the fibers, while matrix swells a little by irradiation-induced point defect. Fiber shrinkage leads to fiber/matrix debonding as being reported by Hollenberg 11) so that elastic modulus and fracture strength are decreased. Therefore, it is needed to optimize the microstructure of SiC/SiC composite (i.e.…”

Section: Introductionmentioning

confidence: 61%

Effect of Fiber Properties on Neutron Irradiated SiC/SiC Composites

Hinoki

Katoh

2002

Mater. Trans.

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The use of SiC/SiC composites for nuclear application has recently been considered because of intrinsic low activation and superior high temperature mechanical properties of SiC. The property of SiC fiber is a key issue in order to improve mechanical properties of SiC/SiC composites following irradiation. SiC/SiC composites with unidirectional fibers were fabricated by chemical vapor infiltration method. Low oxygen and highly crystalline fibers or just low oxygen fibers were used in the composites. The specimens were irradiated at Japan Material Testing Reactor and High Flux Isotope Reactor. The effects of neutron irradiation on mechanical properties were examined by three points flexural test. Microstructure and fracture behavior were observed by scanning electron microscopy before and after neutron irradiation. The SiC/SiC composites with a low oxygen content, near-stoichiometric atomic composition and highly crystalline SiC fibers showed the excellent stability to neutron irradiation. The mechanical property of this material did not degrade, even after neutron irradiation up to 10 dpa, while the other materials with non-highly crystalline SiC fibers degraded significantly.

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“…Raffrey et al [49] found that high cycle efficiency and safety considerations make SiC/SiC materials attractive for use as high performance blankets with LiPb. While the irradiation stability of SiC has always been of concern, it has been established that acceptable properties are expected when the composition of silicon carbide is close to stoichiometric and the microstructure is crystalline [2,[50][51][52][53][54][55]. In a recent study, Hinoki et al found excellent high temperature irradiation resistance for high purity SiC/SiC composites irradiated up to 1600 • C [2].…”

Section: Sic-based Materials In Nuclear Applicationsmentioning

confidence: 99%

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

Zhang¹,

Singh²

2008

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Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These include refractory alloys based on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as those based on silicon carbide (SiC f -SiC); carbon-carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor components is necessary for improved efficiency. Improving thermal conductivity of the materials used in nuclear fuels and other temperature critical components can lower the center-line fuel temperature and thereby enhance durability and reduce the risk of premature failure.Silicon carbide (SiC) is an important ceramic, most commonly used because of its excellent properties such as high strength, high modulus, excellent creep resistance and its high temperature stability. Moreover, crystalline silicon carbide is attracting wide attention as a promising candidate for several applications in nuclear reactors owing to its high thermal conductivity, high melting temperature, good chemical stability, and resistance to swelling under heavy ion bombardment. There have been many efforts to develop SiC based composites in various forms for use in advanced energy systems. However, fabricating SiC based composites by traditional powder processing route generally requires very high temperatures for pressureless sintering. In recent years, with the development of high yield preceramic precursors, the polymer infiltration and pyrolysis (PIP) method has aroused interest for the fabrication of ceramic based materials. Polymer derived ceramic materials offer unique advantages such as ability to fabricate net shaped components, incorporate reinforcements, along with lower processing temperatures, and perhaps most importantly relatively easy control over the microstructure. The raw materials are element-organic polymers whose composition and architecture can be tailored and varied.The primary focus of this work is to use a pyrolysis-based process to fabricate a host of novel silicon carbide-metal carbide/oxide composites, and to synthesize new materials based on mixed-metal (metal/silicon) carbides that cannot be processed using conventional techniques. These mixedcarbide material systems are expected to offer improved material properties for higher-temperature applications. Our fabrication technique resulted in both amorphous and nano-grained SiC matrix composites by controlled pyrolysis of allylhydridopolycarbosilane (AHPCS), the precursor for SiC for our study, under inert argon atmosphere.Cylindrical pellets, φ25 × 25 mm, were fabricated for bulk scale characterization. These samples were analyzed in terms of density and porosity, thermal conductivity, and flexural strength under multiaxial loading conditions. The final composition in the fabricated composite was studied use Xray diffraction (XRD). This was useful in understanding the relative stabil...

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The effect of irradiation on the stability and properties of monolithic silicon carbide and SiCf/SiC composites up to 25 dpa

Cited by 87 publications

References 16 publications

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

Effect of Fiber Properties on Neutron Irradiated SiC/SiC Composites

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

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