Journal of Inorganic Materials, Volume. 37, Issue 8, 821(2022)

Research Progress of SiC Fiber Reinforced SiC Composites for Nuclear Application

Qin OUYANG1...2, Yanfei WANG1,2, Jian XU1,2, Yinsheng LI1, Xueliang PEI1,2, Gaoming MO1,2, Mian LI1,2, Peng LI1, Xiaobing ZHOU1,2, Fangfang GE1,2, Chonghong ZHANG2,3, Liu HE1,2, Lei YANG2,3, Zhengren HUANG1,2, Zhifang CHAI1, Wenlong ZHAN2,3, and Qing HUANG12,* |Show fewer author(s)
Author Affiliations
  • 11. Ningbo Institute of Materials Technology & Engineering, Chinese Academy of Sciences, Ningbo 315201, China
  • 22. Advanced Energy Science and Technology Guangdong Laboratory, Huizhou 516000, China
  • 33. Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
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    References(172)

    [2] Z YANG, F LI, G CHAI. Status and perspective of China’s nuclear safety philosophy and requirements in the post-fukushima era. Frontiers in Energy Research, 819634(2022).

    [8] Y KATOH, L L SNEAD. Silicon carbide and its composites for nuclear applications-historical overview. Journal of Nuclear Materials, 151849(2019).

    [9] K TAKAAKI, K YUTAI, N TAKASHI. Design and strategy for next- generation silicon carbide composites for nuclear energy. Journal of Nuclear Materials, 152375(2020).

    [10] J STEIBEL. Ceramic matrix composites taking flight at GE Aviation. Am. Ceram. Soc. Bull, 32-36(2019).

    [12] M I IDRIS, H KONISHI, M IMAI et al. Neutron irradiation swelling of SiC and SiCf/SiC for advanced nuclear applications, 328-336(2015).

    [18] G E YOUNGBLOOD, R H JONES, A KOHYAMA et al. Radiation response of SiC-based fibers. Journal of Nuclear Materials, 1551-1556(1998).

    [25] J BRAUN, C SAUDER. Mechanical behavior of SiC/SiC composites reinforced with new Tyranno SA4 fibers: effect of interphase thickness and comparison with Tyranno SA3 and Hi- Nicalon S reinforced composites. Journal of Nuclear Materials, 153367(2022).

    [34] T NOZAWA, Y KATOH, L L SNEAD. The effects of neutron irradiation on shear properties of monolayered PyC and multilayered PyC/SiC interfaces of SiC/SiC composites. Journal of Nuclear Materials, 685-691(2007).

    [37] L L SNEAD, E LARA-CURZIO. Interphase integrity of neutron irradiated SiC composites. MRS Online Proceedings Library, 273-278(1998).

    [41] A V UTKIN, A A MATVIENKO, A T TITOV et al. Multiple zirconia interphase for SiC/SiCf composites. Surface and Coatings Technology(2011).

    [42] V PROKIP, V LOZANOV, N MOROZOVA et al. The zirconia- based interfacial coatings on SiC fibers obtained by different chemical methods. Materials Today: Proceedings, 1861-1864(2019).

    [44] N IGAWA, T TAGUCHI, R YAMADA et al. Preparation of silicon-based oxide layer on high-crystalline SiC fiber as an interphase in SiC/SiC composites. Journal of Nuclear Materials, 554-557(2004).

    [59] Y KATOH, M KOTANI, H KISHIMOTO et al. Properties and radiation effects in high-temperature pyrolyzed PIP-SiC/SiC. Journal of Nuclear Materials(2001).

    [67] A KOHYAMA, Y KATOH. Advanced SiC/SiC ceramic composites: developments and applications in energy systems. Ceramic Transactions, 3-18(2002).

    [69] A KOHYAMA, S DONG, Y KATOH. Development of SiC/SiC composites by Nano-Infiltration and Transient Eutectoid (NITE) process. Ceramic Engineering and Science Proceedings, 8(2002).

    [77] G JE. CMC Research at NASA Glenn in 2019: Recent Progress and Plans. NASA: Ceramic & Polymer Composites Branch(2019).

    [85] S K MITAL, B A BEDNARCYK, S M ARNOLD et al. Modeling of melt-infiltrated SiC/SiC composite properties(2009).

    [88] Y FENG, J WANG, N SHANG et al. Multiscale modeling of SiCf/SiC nuclear fuel cladding based on FE-simulation of braiding process. Frontiers in Materials, 634112(2021).

    [89] J TANG, G ZHAO, J WANG et al. Computational geometry- based 3D yarn path modeling of wound SiCf/SiC-cladding tubes and its application to meso-scale finite element model. Frontiers in Materials, 701205(2021).

    [91] P M DOVE, N Z HAN, J J DE YOREO. Mechanisms of classical crystal growth theory explain quartz and silicate dissolution behavior. Proceedings of the National Academy of Sciences of the United States of America, 15357-15362(2005).

    [103] L HALLSTADIUS, S JOHNSON, E LAHODA. Cladding for high performance fuel. Progress in Nuclear Energy, 71-76(2012).

    [105] Y M QIN, X Q LI, C X LIU et al. Effect of deposition temperature on the corrosion behavior of CVD SiC coatings on SiCf/SiC composites under simulated PWR conditions. Corrosion Science, 13(2021).

    [108] P J DOYLE, T KOYANAGI, C ANG et al. Evaluation of the effects of neutron irradiation on first-generation corrosion mitigation coatings on SiC for accident-tolerant fuel cladding. Journal of Nuclear Materials, 152203(2020).

    [109] J Q XI, C LIU, D MORGAN et al. An unexpected role of H during SiC corrosion in water. Journal of Physical Chemistry C, 9394-9400(2020).

    [113] L L SNEAD, T NOZAWA, Y KATOH et al. Handbook of SiC properties for fuel performance modeling. Journal of Nuclear Materials, 377(2007).

    [114] Y R LIN, L G CHEN, C Y HSIEH et al. Atomic configuration of point defect clusters in ion-irradiated silicon carbide. Scientific Reports, 14635(2017).

    [116] P A MOUCHE, C ANG, T KOYANAGI et al. Characterization of PVD Cr, CrN, and TiN coatings on SiC. Journal of Nuclear Materials, 151781(2019).

    [117] S S RAIMAN, C ANG, P DOYLE et al. Hydrothermal corrosion of SiC materials for accident tolerant fuel cladding with and without mitigation coatings, 259-267(2017).

    [119] R ISHIBASHI, K ISHIDA, T KONDO et al. Corrosion-resistant metallic coating on silicon carbide for use in high-temperature water. Journal of Nuclear Materials, 153214(2021).

    [120] P J DOYLE, C ANG, L SNEAD et al. Hydrothermal corrosion of first-generation dual-purpose coatings on silicon carbide for accident- tolerant fuel cladding. Journal of Nuclear Materials, 152695(2021).

    [133] M SINGH. Joining of sintered silicon carbide ceramics for high- temperature applications. Journal of Materials Science Letters, 459-461(1998).

    [172] K HOJOU, S FURUNO, K N KUSHITA et al. EELS analysis of SiC crystals under hydrogen and helium dual-ion beam irradiation. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms(1998).

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    Qin OUYANG, Yanfei WANG, Jian XU, Yinsheng LI, Xueliang PEI, Gaoming MO, Mian LI, Peng LI, Xiaobing ZHOU, Fangfang GE, Chonghong ZHANG, Liu HE, Lei YANG, Zhengren HUANG, Zhifang CHAI, Wenlong ZHAN, Qing HUANG. Research Progress of SiC Fiber Reinforced SiC Composites for Nuclear Application[J]. Journal of Inorganic Materials, 2022, 37(8): 821

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    Paper Information

    Category: REVIEW

    Received: Mar. 16, 2022

    Accepted: --

    Published Online: Jan. 10, 2023

    The Author Email: HUANG Qing (huangqing@nimte.ac.cn)

    DOI:10.15541/jim20220145

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