Evaluation of neutron irradiated near-stoichiometric silicon carbide fiber composites

Snead, Lance Lewis; Katoh, Yutai; Kohyama, Akira; Bailey, Jeffrey L; Vaughn, N.L.; Lowden, R.A.

doi:10.1016/s0022-3115(00)00235-x

Cited by 79 publications

(41 citation statements)

References 10 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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“…It is generally agreed that a-SiC, undergoes swelling under neutron irradiation, which may not be insignificant even at lower temperatures, making it unsuitable for nuclear applications. In a parallel study by Zunjarrao et al [67], it was observed that pyrolysis to 1150-1650 • C produces β-crystalline silicon carbide from AHPCS, which would be more suitable for nuclear applications [53,54,94]. Finally it should be noted that allylhydridopolycarbosilane, the precursor used in this study, is known for its ultra high purity and ability to form near-stoichiometric SiC, which are favorable attributes for nuclear applications of SiC.…”

Section: Discussionmentioning

confidence: 60%

“…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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“…[2][3][4][5][6] SiC/SiC composites reinforced with less crystalline and non-stoichiometric SiC fibers have shown the interfacial debonding due to mismatch of swelling behavior of the fiber and -SiC matrix after neutron irradiation. In contrast, due to highly crystalline and near stoichiometric SiC fibers, advanced SiC/SiC composites have exhibited excellent irradiation stability in ultimate bend/tensile strength.…”

Section: Introductionmentioning

confidence: 99%

“…In contrast, due to highly crystalline and near stoichiometric SiC fibers, advanced SiC/SiC composites have exhibited excellent irradiation stability in ultimate bend/tensile strength. 6,7) In our previous work, 8) tensile, flexural and inter-laminar shear properties of advanced SiC/SiC composites with various interfaces (pyrolytic carbon (PyC), multilayered SiC/PyC (ML) and pseudo-porous SiC) after neutron irradiation up to 1 Â 10 25 n/m 2 at mainly 1023 K was examined. Advanced SiC/SiC composites exhibited good irradiation resistance in ultimate bend/tensile strength, but the result of a slight loss of proportional limit stress (PLS) in the monotonic tensile test and $40% degradation of interlaminar shear strength in the double notched specimen (DNS) test suggested degradation of F/M interphase.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of Fiber/Matrix Interfacial Strength of Neutron Irradiated SiC/SiC Composites Using Hysteresis Loop Analysis of Tensile Test

et al. 2006

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Advanced SiC/SiC composites composed of highly-crystalline and near-stoichiometric SiC fibers, SiC matrix by CVI method, and PyC interphase were irradiated up to 1:0 Â 10 25 n/m 2 (E > 0:1 MeV, $1 dpa) at 1273 K. Unload/reload cyclic tensile test and hysteresis loop analysis were carried out in order to identify neutron irradiation effects on interfacial properties of advanced SiC/SiC. The composites exhibited good irradiation resistance in ultimate tensile strength ($10% increase), but there were slight reduction of elastic modulus and proportional limit stress (PLS) ($10%). Wider hysteresis loops and lower gradient of the curves beyond PLS from the strain-stress curves, and longer pullouts of fiber from the SEM observation were observed, which imply weaker F/M interactions after neutron irradiation. From the hysteresis loop analysis, degradation of interfacial sliding stress and negative increment of misfit stress after neutron irradiation were obtained.

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Evaluation of neutron irradiated near-stoichiometric silicon carbide fiber composites

Cited by 79 publications

References 10 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

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

Evaluation of Fiber/Matrix Interfacial Strength of Neutron Irradiated SiC/SiC Composites Using Hysteresis Loop Analysis of Tensile Test

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