核用SiC复合包壳多尺度力学损伤研究方法评述

doi:10.15541/jim20250494

无机材料学报 ›› 2026, Vol. 41 ›› Issue (9): 1157-1177.DOI: 10.15541/jim20250494

• 综述 • 下一篇

核用SiC复合包壳多尺度力学损伤研究方法评述

黄淦¹^,²(), 薛佳祥²(), 檀财旺¹(), 刘洋², 张国梁², 杨正茂³, 陈招科⁴

¹ 哈尔滨工业大学材料结构精密焊接与连接全国重点实验室, 哈尔滨 150001
² 中广核研究院有限公司核燃料与材料研究所, 深圳 518026
³ 中国科学院力学研究所, 北京 100190
⁴ 中南大学粉末冶金全国重点实验室, 长沙 410083

收稿日期:2025-12-14 修回日期:2026-02-09 出版日期:2026-09-20 网络出版日期:2026-02-28
通讯作者: 薛佳祥, 教授级高级工程师. E-mail: jiaxiang_xue@163.com;
檀财旺, 教授. E-mail: tancaiwang@hitwh.edu.cn
作者简介:黄淦(2003-), 男, 博士研究生. E-mail: 24B909009@stu.hit.edu.cn
基金资助:
国家自然科学基金(U24B2028)

Multi-scale Methods for Investigating Mechanical Damage in Nuclear SiC Composite Cladding: A Review

HUANG Gan¹^,²(), XUE Jiaxiang²(), TAN Caiwang¹(), LIU Yang², ZHANG Guoliang², YANG Zhengmao³, CHEN Zhaoke⁴

¹ State Key Laboratory of Precision Welding & Joining of Materials and Structures, Harbin Institute of Technology, Harbin 150001, China
² Nuclear Fuel and Materials Research Institute, China Nuclear Power Technology Research Institute, Shenzhen 518026, China
³ Institute of Mechanics, Chinese Academy of Sciences, Beijing 100190, China
⁴ State Key Laboratory of Powder Metallurgy, Central South University, Changsha 410083, China

Received:2025-12-14 Revised:2026-02-09 Published:2026-09-20 Online:2026-02-28
Contact: XUE Jiaxiang, professor. E-mail: jiaxiang_xue@163.com;TAN Caiwang, professor. E-mail: tancaiwang@hitwh.edu.cn
About author:HUANG Gan (2003-), male, PhD candidate. E-mail: 24B909009@stu.hit.edu.cn
Supported by:
National Natural Science Foundation of China(U24B2028)

摘要/Abstract

摘要：

SiC复合包壳因其高比强度、耐中子辐照和抗高温氧化等特性, 有望替代传统锆合金包壳的颠覆性核燃料包壳技术。然而, SiC复合包壳结构复杂, 在服役条件下的力学失效行为尚不明确, 制约了技术迭代与应用。为深入揭示SiC复合包壳损伤机理、预测极端环境下应力开裂风险并推进其工程应用, 需开展系统性的多尺度力学损伤研究。本文围绕核用SiC复合包壳的多尺度力学损伤研究方法进行评述, 涵盖宏观及微纳力学试验, 基于数字图像相关、X射线计算机断层扫描和声发射等技术的原位监测与原位电镜表征, 以及多尺度数值仿真等方面。目前该领域已取得重要进展: 宏观力学测试可有效表征SiC复合包壳的整体力学性能, 多种原位监测技术实现了包壳从表面到内部、从静态到动态的多维损伤演化观测, 微纳力学测试为获取纤维、基体及界面等微区组元的力学参数提供了支撑, 多尺度数值仿真则构建了从微观机制到宏观响应的有效关联与预测桥梁。最后, 本文对该领域未来发展趋势与挑战进行了展望。

关键词: 核用SiC复合包壳, 多尺度力学测试, 原位表征, 多尺度数值仿真, 综述

Abstract:

Silicon carbide (SiC) composite cladding has emerged as a disruptive fuel cladding technology in advanced nuclear energy systems, owing to its high specific strength, remarkable neutron irradiation resistance, and excellent high-temperature oxidation resistance, demonstrating significant potential to replace conventional zirconium alloy cladding. However, the structural complexity of SiC composites hinders a comprehensive understanding of their mechanical failure behavior under service conditions, which in turn constrains the pace of technological iteration. Therefore, to deeply reveal the damage mechanism of SiC composite cladding, accurately predict its stress-cracking risk in extreme environments, and further accelerate its engineering application, systematic multi-scale mechanical damage studies are essential. This review focuses on the research methodologies employed in multi-scale mechanical damage investigation of nuclear-grade SiC composite cladding. It covers macroscopic and micro-/nano-mechanical testing, in-situ monitoring and characterization techniques such as digital image correlation, X-ray computed tomography, and acoustic emission, as well as in-situ electron microscopy characterization and multi-scale numerical simulation. Significant progress has been achieved in this field: macroscopic mechanical tests can effectively characterize the overall mechanical performance of SiC composite cladding; multiple in-situ techniques enable multi-dimensional tracking of damage evolution from surface to interior and from static to dynamic processes; micro-/nano-mechanical testing provides critical support for obtaining mechanical parameters of key micro-constituents, including fibers, matrix, and interfaces; and multi-scale numerical simulations have established a predictive framework that effectively correlates microscopic mechanisms with macroscopic responses. Finally, prospects for future development and remaining challenges in this research area are outlined.

Key words: nuclear SiC composite cladding, multi-scale mechanical testing, in-situ characterization, multi-scale numerical simulation, review

中图分类号:

TB332

黄淦, 薛佳祥, 檀财旺, 刘洋, 张国梁, 杨正茂, 陈招科. 核用SiC复合包壳多尺度力学损伤研究方法评述[J]. 无机材料学报, 2026, 41(9): 1157-1177.

HUANG Gan, XUE Jiaxiang, TAN Caiwang, LIU Yang, ZHANG Guoliang, YANG Zhengmao, CHEN Zhaoke. Multi-scale Methods for Investigating Mechanical Damage in Nuclear SiC Composite Cladding: A Review[J]. Journal of Inorganic Materials, 2026, 41(9): 1157-1177.

图/表 16

图1 压水堆燃料组件[5]与SiC复合包壳的结构示意图

Fig. 1 Schematic diagrams of the structure of the pressurized water reactor fuel assembly[5] and the SiC composite cladding (a) Pressurized water reactor fuel rod bundle assembly[5]; (b) SiC composite cladding tube

图2 SiC复合包壳宏观力学试验示意图[16,23,32,34]

Fig. 2 Schematic diagrams of macroscopic mechanical tests for SiC composite cladding[16,23,32,34] (a) Uniaxial tension[16]; (b) Expansion due compression[23]; (c) Hydraulic burst test[32]; (d) C-ring compression[34]

图3 单/双编织层厚裸SiC管的四点弯曲试验结果及SEM断口形貌[49]

Fig. 3 Four-point bending test results and SEM fracture surfaces of single/double-layer SiC braided tubes[49] (a) Single-layer; (b) Double-layer; (c) SEM fracture surfaces

表1 宏观力学测试方法简要对比

Table 1 Brief comparison of macro-mechanical testing methods

Testing method	Core function	Key advantages	Main limitations
Uniaxial tension test	To obtain axial intrinsic mechanical properties (modulus, strength)	Standardized method, direct quantification of axial response	Primarily reflecting axial performance, differing from the actual hoop-stress-dominated stress state
Expansion due compression test	To evaluate the hoop strength and failure behavior of tubular specimens	Simple operation, short setup time	Suitable only for short tubes, prone to stress concentration leading to premature local failure
Hydraulic burst test	To evaluate the hoop strength and failure behavior of tubular specimens	Fluid medium ensures uniform hoop stress distribution, applicable to tubes of various lengths	Complex operation, high cost, safety risks from seal failure or fluid jetting
C-ring compression test	To determine hoop strength, especially suitable for high-temperature testing	Minimal sample requirement, easy implementation, ideal for high- temperature screening	Sensitive to defect distribution due to significant stress concentration
Four-point bending test	To assess flexural performance and overall structural integrity	Four-point bending provides a uniform and stable bending stress field	Absence of well-established research and standards for tubular specimens

图4 DIC计算的SiC包壳表面环向应变εhoop在不同载荷下的图像[60]

Fig. 4 Images of the circumferential strain εhoop on the surface of the SiC cladding calculated by DIC[60] (a) Fault map under 0 N load; (b-d) Strain εhoop measurement results obtained within the elastic range: (b) 2100 N, (c) 2500 N, (d) 2730 N

图5 原位XCT监测下的多涂层SiC复合包壳高温C环压缩失效行为[69]

Fig. 5 Compressive failure behavior of multi-coated SiC composite cladding in high temperature C-ring under in-situ XCT monitoring[69] (a) Meso-structure of the cladding tube showing the multi-layer coating and CMC matrix; (b) Schematic of the in-situ high-temperature C-ring compression test coupled with 3D-XCT imaging; (c) Real-time crack propagation and failure mechanisms at room temperature and 1200 ℃ under different load levels (0.58PU and 0.73PU, where PU is the maximum load applied (peak load))

图6 声发射监测下的三层SiC复合包壳的准静态径向压缩实验[85]

Fig. 6 Quasi-static radial compression experiment of a three-layer SiC composite cladding under acoustic emission monitoring[85] (a) Schematic diagram of the test site; (b) Test equipment and test sample; (c) Schematic diagram of acoustic emission acquisition

图7 纳米压痕试验示例结果及纤维TEM照片[91]

Fig. 7 Example results of nanoindentation test and TEM images of fibers[91] (a) Nanoindentation illustration; (b) Radial distribution of the inclusions within a fiber; (c) Relationship between hardness and modulus varying with depth; (d) Cross-section of a fiber; (e) Inclusions at the grain boundaries of fibers; (f) EDX linescan signals of C and Si

图8 纤维顶出测试示意图[94]

Fig. 8 Schematic diagram of fiber push-out[94] (a) Sample preparation; (b) Process of fiber push-out

图9 微柱在微柱压缩试验后的SEM照片[110]

Fig. 9 SEM images of the micro-pillar after micro-pillar compression test[110] (a) Remaining part of the 55° pillar; (b) Top piece removed from the 55° pillar

图10 微柱压缩测量PyC界面层断裂韧性示意图[111]

Fig. 10 Schematic diagrams illustrating the microcolumn compression measurement of the fracture toughness of the PyC interface layer[111] (a, b) Schematic diagrams of microcolumn compression test; (c) Stress state and force balance of typical microcolumn compression structures; (d) Performance of interface layers of different thicknesses

图11 平行晶粒生长方向的微悬臂梁测试前(a)、后(b)的SEM照片[119]

Fig. 11 SEM images of a parallel oriented micro-cantilever before (a) and after (b) testing[119]

表2 微纳力学测试方法简要对比

Table 2 Brief comparison of micro-/nano-mechanical testing methods

Testing Method	Core function	Key advantages	Main limitations
Nanoindentation	To measure hardness and elastic modulus of micro-regions (fiber, matrix, etc.)	Relatively simple sample preparation, enabling rapid property mapping via arrays	Susceptible to size effects and matrix constraint effects
Push-out/Push-in	To characterize the interfacial shear strength between fiber and matrix	Enabling direct use of bulk samples via push-in technique, avoiding preparation-induced damage	Requiring validation with other techniques due to indirect signal interpretation
Micro-pillar compression	To obtain the intrinsic strength and deformation behavior of micro-regions (e.g., interface)	Providing robust data via simple stress state, offering a realistic measure of interfacial bonding	Time-consuming FIB preparation with potential damage and significant size effects
Micro-cantilever bending	To measure the fracture toughness of micro-regions (fiber, matrix, etc.)	Enabling direct measurement of fracture toughness parameters	Highly dependent on precise FIB machining, which is complex and time-consuming

图12 不同水平载荷下的表面裂纹扩展路径SEM照片[125]

Fig. 12 SEM images of surface crack propagation paths under different load levels[125] In unreinforced matrix region: (a) 60 MPa, (b) 65 MPa, (c) 70 MPa; In transverse fiber bundles: (d) 60 MPa, (e) 65 MPa; In longitudinal fiber bundles: (f) 70 MPa

图13 SiCf/SiC复合材料的微观RVE模型与不同加载条件下的累积应变等值线图[133]

Fig. 13 Micro-scale RVE model of SiCf/SiC composite material and the contour maps of cumulative strain under different loading conditions[133] (a) Random fiber distribution; (b) Fiber groups; (c) Matrix groups; (d) Interface groups and contour maps of cumulative strain under different loading conditions; (e) Transverse tension; (f) Transverse compression; (g) Out-of-plane shear

图14 SiC纤维束的RVE模型和三种不同的SiC内外编织结构模型[134]

Fig. 14 RVE model of SiC fiber bundle and three different models of SiC internal and external weaving structures[134] (a) SiC fiber bundle RVE model; (b) Braided structure inside B1; (c) Braided structure outside B1; (d) Braided structure inside B2; (e) Braided structure outside B2; (f) Braided structure inside B3; (g) Braided structure outside B3

参考文献 142

[1]	荆春宁, 高力, 马佳鹏, 等. “碳达峰、碳中和”背景下能源发展趋势与核能定位研判. 核科学与工程, 2022, 42(1): 1.
[2]	YANG Z, LI F, CHAI G. Status and perspective of China’s nuclear safety philosophy and requirements in the post-Fukushima era. Frontiers in Energy Research, 2022, 9: 819634. DOI URL
[3]	STONE J, SCHLEICHER R, DECK C, et al. Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding. Journal of Nuclear Materials, 2015, 466: 682. DOI URL
[4]	LI Y, YOU E, WANG T, et al. Developments, challenges and prospects in thermal-hydraulic research on accident tolerant fuel. Heliyon, 2024, 10(19): e38999.
[5]	TANG C, STUEBER M, SEIFERT H, et al. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings. Corrosion Reviews, 2017, 35(3): 141.
[6]	PHAM H, KURATA M, STEINBRUECK M. Steam oxidation of silicon carbide at high temperatures for the application as accident tolerant fuel cladding, an overview. Thermo, 2021, 1(2): 151.
[7]	TERRANI K. Accident tolerant fuel cladding development: promise, status, and challenges. Journal of Nuclear Materials, 2018, 501: 13. DOI URL
[8]	LEE Y, NO H, LEE J. Design optimization of multi-layer silicon carbide cladding for light water reactors. Nuclear Engineering and Design, 2017, 311: 213. DOI URL
[9]	LI Y, CHEN Z, ZHANG R, et al. Ring compression properties of SiC_f/SiC composites prepared by chemical vapor infiltration. Ceramics International, 2018, 44(18): 22529.
[10]	DECK C, JACOBSEN G, SHEEDER J, et al. Characterization of SiC-SiC composites for accident tolerant fuel cladding. Journal of Nuclear Materials, 2015, 466: 667. DOI URL
[11]	QIU B, WANG J, DENG Y, et al. A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti₃SiC₂ for ATF cladding. Nuclear Engineering and Technology, 2020, 52(1): 1.
[12]	WU X, ZHENG R, LI L, et al. Research progress on in-situ monitoring of damage behavior of SiC_f/SiC ceramic matrix composites at high temperature environments. Journal of Inorganic Materials, 2024, 39(6): 609.
[13]	PU J, WANG J, TANG J, et al. Multi-scale progressive damage and failure behavior analysis of three-dimensional winding SiC fiber-reinforced SiC matrix composite tube. Applied Composite Materials, 2023, 30(5): 1605.
[14]	REIS P, MAGALHÃES I, FARIA R, et al. Accident tolerant fuels behavior analysis for pressurized water reactor in steady state and transient conditions. Nuclear Engineering and Design, 2023, 415: 112673. DOI URL
[15]	ASTM International. Standard test method for monotonic axial tensile behavior of contnuous fiber-reinforced advanced ceramic tubular test specimens at ambient temperature: ASTM C1773. West Conshohocken: ASTM International, 2013.
[16]	SHAPOVALOV K, JACOBSEN G, ALVA L, et al. Strength of SiC_f-SiC_m composite tube under uniaxial and multiaxial loading. Journal of Nuclear Materials, 2018, 500: 280. DOI URL
[17]	KATOH Y, OZAWA K, SHIH C, et al. Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: properties and irradiation effects. Journal of Nuclear Materials, 2014, 448(1/2/3): 448.
[18]	MORSCHER G H, YUN H M, DICARLO J A. In-plane cracking behavior and ultimate strength for 2D woven and braided melt-infiltrated SiC/SiC composites tensile loaded in off-axis fiber directions. Journal of the American Ceramic Society, 2007, 90(10): 3185.
[19]	NOZAWA T, OZAWA K, CHOI Y, et al. Determination and prediction of axial/off-axial mechanical properties of SiC/SiC composites. Fusion Engineering and Design, 2012, 87(5/6): 803.
[20]	CHEN Y, GÉLÉBART L, CHATEAU C, et al. Crack initiation and propagation in braided SiC/SiC composite tubes: effect of braiding angle. Journal of the European Ceramic Society, 2020, 40(13): 4403.
[21]	SINGH G, SWEET R, BROWN N R, et al. Parametric evaluation of SiC/SiC composite cladding with UO₂ fuel for LWR applications: fuel rod interactions and impact of nonuniform power profile in fuel rod. Journal of Nuclear Materials, 2018, 499: 155. DOI URL
[22]	SINGH G, TERRANI K, KATOH Y. Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis. Journal of Nuclear Materials, 2018, 499: 126. DOI URL
[23]	XIAO M, LUO H, YOU X, et al. Hoop tensile properties and crack propagation investigation of 2D braided SiC_f/SiC composite tubes: experiments and simulations. Journal of Nuclear Materials, 2025, 603: 155433. DOI URL
[24]	MOSLEY K. The stressing for test purposes of materials in tubular form using elastomeric inserts—experimental and theoretical development. Proceedings of the Institution of Mechanical Engineers, 1982, 196(1): 123.
[25]	ASTM International. Standard test method for hoop tensile strength of continuous fiber-reinforced advanced ceramic composite tubular test specimens at ambient temperature using elastomeric inserts: ASTM C 1819. West Conshohocken: ASTM International, 2015.
[26]	ZHANG Z, GUAN J, CHEN J, et al. Response to internal pressure shock and hoop strength of SiC_f/SiC cladding. Journal of the European Ceramic Society, 2024, 44(11): 6298.
[27]	KIM D, LEE H, PARK J, et al. Fabrication and measurement of hoop strength of SiC triplex tube for nuclear fuel cladding applications. Journal of Nuclear Materials, 2015, 458: 29. DOI URL
[28]	NANCE J, SUBHASH G, SANKAR B, et al. Influence of weave architecture on mechanical response of SiC_f-SiC_m tubular composites. Materials Today Communications, 2022, 33: 104206. DOI URL
[29]	CINBIZ M, KOYANAGI T, SINGH G, et al. Failure behavior of SiC/SiC composite tubes under strain rates similar to the pellet-cladding mechanical interaction phase of reactivity-initiated accidents. Journal of Nuclear Materials, 2019, 514: 66. DOI URL
[30]	VERRILLI M, DICARLO J, CALOMINO A, et al. Hoop tensile properties of ceramic matrix composite cylinders. Journal of Testing and Evaluation, 2005, 33(5): 370.
[31]	CAIN J, CASE S, LESKO J. Testing of hygrothermally aged e-glass/epoxy cylindrical laminates using a novel fixture for simulating internal pressure. Journal of Composites for Construction, 2009, 13(4): 325.
[32]	ROHMER E, MARTIN E, LORRETTE C. Mechanical properties of SiC/SiC braided tubes for fuel cladding. Journal of Nuclear Materials, 2014, 453(1/2/3): 16.
[33]	DASSIOS K, AGGELIS D, KORDATOS E, et al. Cyclic loading of a SiC-fiber reinforced ceramic matrix composite reveals damage mechanisms and thermal residual stress state. Composites Part A: Applied Science and Manufacturing, 2013, 44: 105. DOI URL
[34]	ASTM International. Standard test method for ultimate strength of advanced ceramics with diametrally compressed C-ring specimens at ambient temperature: ASTM C1323. West Conshohocken: ASTM International, 2010.
[35]	International Organization for Standardization.Fine ceramics (advanced ceramics, advanced technical ceramics) — Test method for determining elastic modulus and bending strength of ceramic tube and rings: ISO 18558:2015 Geneva, Switzerland: International Organization for Standardization, 2015.
[36]	JACOBSEN G, STONE J, KHALIFA H, et al. Investigation of the C-ring test for measuring hoop tensile strength of nuclear grade ceramic composites. Journal of Nuclear Materials, 2014, 452(1/3): 125.
[37]	ZHAN C, LIU Y, CHEN J, et al. Hoop tensile properties of SiC fiber-reinforced SiC matrix composite tubes with/without CVD-SiC coating. Journal of the European Ceramic Society, 2024, 44(14): 116707.
[38]	DRIEUX P, CHOLLON G, JACQUES S, et al. Synthesis and characterization of monolithic CVD-SiC tubes. Journal of the European Ceramic Society, 2016, 36(8): 1873.
[39]	SHAPOVALOV K, JACOBSEN G, SHIH C, et al. C-ring testing of nuclear grade silicon carbide composites at temperatures up to 1900 ℃. Journal of Nuclear Materials, 2019, 522: 184. DOI URL
[40]	WANG L, WEI B, WANG D, et al. Novel α/β SiC-(Ti, Nb)B₂ toughened (Ti, Nb)C-based composites with enhanced mechanical properties fabricated by in situ reactions sintering at low temperature. Ceramics International, 2024, 50(22): 46211.
[41]	DECK C, KHALIFA H, JACOBSEN G, et al. Demonstration of engineered multi-layered SiC-SiC cladding with enhanced accident tolerance. Proceedings of the 2018 Water Reactor Fuel Performance Meeting, Prague, 2018.
[42]	WANG H, ZHOU X, PENG S, et al. Fabrication, microstructures and properties of SiC_f/SiC composites prepared with two kinds of SiC fibers as reinforcements. New Carbon Materials, 2019, 34(2): 181.
[43]	YANG J, STEINBRÜCK M, TANG C, et al. Review on chromium coated zirconium alloy accident tolerant fuel cladding. Journal of Alloys and Compounds, 2022, 895: 162450. DOI URL
[44]	ASTM International. Standard test method for flexural properties of continuous fiber-reinforced advanced ceramic composites: ASTM C1341. West Conshohocken: ASTM International, 2006.
[45]	DECK C, KHALIFA H, SAMMULI B, et al. Fabrication of SiC-SiC composites for fuel cladding in advanced reactor designs. Progress in Nuclear Energy, 2012, 57: 38. DOI URL
[46]	WEI Y, YE F, CHENG L, et al. Effects of in-situ carbon layer and volume fraction of SiC fiber on the mechanical properties and fracture behaviors of SiC_f/SiC composites fabricated by a modified PIP method. Journal of the European Ceramic Society, 2023, 43(4): 1397.
[47]	KOYANAGI T, KATOH Y. Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions. Journal of Nuclear Materials, 2017, 494: 46. DOI URL
[48]	NANCE J, THANDAGA H, SUBHASH G, et al. Failure characterization of SiC/SiC woven tubular composites. Gainesville: University of Florida, 2019.
[49]	ROOYEN I, LLOYD W, TROWBRIDGE T, et al. SiC-CMC-zircaloy-4 nuclear fuel cladding performance during 4-point tubular bend testing. Idaho Falls: Idaho National Laboratory (INL), 2013.
[50]	FLAUDER S, LANGHOF N, KRENKEL W, et al. Size effect of carbon fiber-reinforced silicon carbide composites (C/C-SiC): part 1-bending load and statistical effects. Journal of the European Ceramic Society, 2021, 41(14): 6805.
[51]	HEYER A, BRACQ A, ROSSIT J, et al. Methodology for strength distribution estimation of ceramics from ball-on-three-balls and four-point bending experiments, Weibull statistics and fractographic investigations: application to magnesium aluminum spinel. Ceramics International, 2023, 49(19): 31988.
[52]	XI L, JINQUAN D, JINCHAO P, et al. Tensile damage mechanism analysis and mesoscale modeling of plain-woven SiC_f/SiC ceramic matrix composite based on in-situ synchrotron radiation experiments. Journal of Materials Research and Technology, 2025, 38: 4005. DOI URL
[53]	DU Y, ZHANG D, WANG L, et al. Damage mechanism characterization of plain weave ceramic matrix composites under in-plane shear using in-situ X-ray micro-CT and deep-learning- based image segmentation. Journal of the European Ceramic Society, 2024, 44(1): 142.
[54]	WU X, ZHENG R, LI L, et al. Damage mechanism identification and failure behavior of 2D needle-punched SiC_f/SiC composites based on acoustic emission and digital image correlation. Materials Characterization, 2024, 218: 114491. DOI URL
[55]	SONG J, WANG L, HUANG J, et al. Mechanical behavior of 2D woven SiC_f/SiC composites investigated by acoustic emission and digital image correlation. Ceramics International, 2022, 48(23): 35340.
[56]	WANG F, TENG X, HU X, et al. Damage and failure analysis of a SiC_f/SiC ceramic matrix composite using digital image correlation and acoustic emission. Ceramics International, 2022, 48(4): 4699.
[57]	BUMGARDNER C, HEIM F, ROACHE D, et al. Characterizing environment-dependent fracture mechanisms of ceramic matrix composites via digital image correlation. Journal of the American Ceramic Society, 2021, 104(12): 6545.
[58]	HOLMES J, SOMMACAL S, DAS R, et al. Digital image and volume correlation for deformation and damage characterization of fibre-reinforced composites: a review. Composite Structures, 2023, 315: 116994. DOI URL
[59]	BERNACHY-BARBE F, GÉLÉBART L, BORNERT M, et al. Characterization of SiC/SiC composites damage mechanisms using digital image correlation at the tow scale. Composites Part A: Applied Science and Manufacturing, 2015, 68: 101. DOI URL
[60]	CROOM B, XU P, LAHODA E, et al. Quantifying the three-dimensional damage and stress redistribution mechanisms of braided SiC/SiC composites by in situ volumetric digital image correlation. Scripta Materialia, 2017, 130: 238. DOI URL
[61]	CHI Y, YU L, PAN B. Low-cost, portable, robust and high-resolution single-camera stereo-DIC system and its application in high-temperature deformation measurements. Optics and Lasers in Engineering, 2018, 104: 141. DOI URL
[62]	LIU B, LAN S, LI J, et al. Digital image correlation in extreme conditions. Thin-Walled Structures, 2024, 205: 112589. DOI URL
[63]	WANG H, KOYANAGI T, ARREGUI D, et al. Anisotropic thermal diffusivity and conductivity in SiC/SiC tubes studied by infrared imaging and X-ray computed tomography. Ceramics International, 2022, 48(15): 21717.
[64]	WU S, XIAO T, WITHERS P. The imaging of failure in structural materials by synchrotron radiation X-ray microtomography. Engineering Fracture Mechanics, 2017, 182: 127. DOI URL
[65]	CHEN Y, GÉLÉBART L, CHATEAU C, et al. 3D detection and quantitative characterization of cracks in a ceramic matrix composite tube using X-ray computed tomography. Experimental Mechanics, 2020, 60(3): 409.
[66]	CHEN Y, GÉLÉBART L, CHATEAU C, et al. Analysis of the damage initiation in a SiC/SiC composite tube from a direct comparison between large-scale numerical simulation and synchrotron X-ray micro-computed tomography. International Journal of Solids and Structures, 2019, 161: 111. DOI URL
[67]	SAUCEDO-MORA L, LOWE T, ZHAO S, et al. In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite. Journal of Nuclear Materials, 2016, 481: 13. DOI URL
[68]	YUAN G, FORNA J, XU P, et al. In situ high-temperature 3D imaging of the damage evolution in a SiC nuclear fuel cladding material. Materials & Design, 2023, 227: 111784.
[69]	YUAN G, COOK D, BARNARD H, et al. Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 ℃. Materials & Design, 2025, 256: 114260.
[70]	CHATEAU C, GÉLÉBART L, BORNERT M, et al. In situ X-ray microtomography characterization of damage in SiC_f/SiC minicomposites. Composites Science and Technology, 2011, 71(6): 916.
[71]	CAKMAK E, CINBIZ M N, ARREGUI J, et al. Damage progression and failure of SiC/SiC composite tubes under hard-contact radial expansion. Composites Part B: Engineering, 2025, 307: 112869. DOI URL
[72]	DENG Y, HAO Y, ZHANG C, et al. Fracture toughness evolution and failure mechanisms of two-dimensional SiC_f/SiC composites at temperatures up to 1500 ℃ in air. Theoretical and Applied Fracture Mechanics, 2024, 131: 104458. DOI URL
[73]	LU W, WANG Z, CHEN Y, et al. Flexural property and failure mechanism of C/SiC composites investigated by high-temperature three-point bending and in-situ X-ray computed tomography. Journal of the European Ceramic Society, 2025, 46: 117952. DOI URL
[74]	GAO Y, WANG Y, YANG X, et al. Synchrotron X-ray tomographic characterization of CVI engineered 2D-woven and 3D-braided SiC_f/SiC composites. Ceramics International, 2016, 42(15): 17137.
[75]	LI Q, CHEN Y, CHEN Y, et al. Effects of void defects on fracture features and tensile strength of C/SiC composites: an image-based FEM study. Applied Composite Materials, 2022, 29(3): 1021.
[76]	LIN Q, ZHONG S, ZHANG X, et al. Study on registration and fusion methods for neutron/X-ray three-dimensional tomography images. NDT & E International, 2025, 158: 103567. DOI URL
[77]	KANG F, MEI H, GAO X, et al. Three-dimensional in-situ observation and cohesive zone modeling of tension-induced delamination of two-dimensional C/SiC composites via deep learning-based damage identification. Carbon, 2025, 233: 119842. DOI URL
[78]	ZHU R, NIU G, QU Z, et al. In-situ quantitative tracking of micro-crack evolution behavior inside CMCs under load at high temperature: a deep learning method. Acta Materialia, 2023, 255: 119073. DOI URL
[79]	GAO X, LEI B, ZHANG Y, et al. Identification of microstructures and damages in silicon carbide ceramic matrix composites by deep learning. Materials Characterization, 2023, 196: 112608. DOI URL
[80]	BADRAN A, MARSHALL D, LEGAULT Z, et al. Automated segmentation of computed tomography images of fiber-reinforced composites by deep learning. Journal of Materials Science, 2020, 55(34): 16273.
[81]	MORSCHER G, MAILLET E. 5.12 Nondestructive evaluation-use of acoustic emission for CMCs. Comprehensive Composite Materials II, 2018, 5: 308.
[82]	SWAMINATHAN B, MCCARTHY N, ALMANSOUR A, et al. Microscale characterization of damage accumulation in CMCs. Journal of the European Ceramic Society, 2021, 41(5): 3082.
[83]	BROCKMAN C, ALMANSOUR A, KISER J, et al. Acoustic emission monitoring of temperature-dependent tensile behavior of unidirectional SiC_f/SiC ceramic matrix composites. Journal of the European Ceramic Society, 2025, 45(10): 117350.
[84]	NOZAWA T, KOYANAGI T, KATOH Y, et al. Failure evaluation of neutron-irradiated SiC/SiC composites by underwater acoustic emission. Journal of Nuclear Materials, 2022, 566: 153787. DOI URL
[85]	ZHOU J, LIN B, SUI T, et al. Radial compression characteristics and damage evolution of three-layer SiC_f/SiC composite tubes based on acoustic emission. Journal of the European Ceramic Society, 2025, 45(16): 117673.
[86]	杨丽, 周益春, 朱旺. 热障涂层失效的声发射实时表征技术研究进展. 中国材料进展, 2020, 39(11): 878.
[87]	FRAZER D, HOSEMANN P. Nanoindentation-based techniques for evaluating irradiated fuel and structural materials// BEAKE B, LISKIEWICZ T. Nanomechanics for coatings and engineering surfaces. Elsevier, 2025: 571-597.
[88]	ZHEN X, LI L, ZHENG R, et al. Optimized interfacial evaluation methods of SiC_f/SiC composites: fiber push-out, fiber push-in and micropillar compression. Materials Characterization, 2025, 223: 114873. DOI URL
[89]	OLIVER W, PHARR G. An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments. Journal of Materials Research, 2012, 7(6): 1564.
[90]	MA Y, YANG S, MENG X, et al. Heat treatment effects on microstructure and mechanical properties of CVI SiC_f/PyC/SiC composites with Cansas-Ⅲ SiC fibers. Journal of the European Ceramic Society, 2023, 43(14): 5940.
[91]	ZAYACHUK Y, KARAMCHED P, DECK C, et al. Linking microstructure and local mechanical properties in SiC-SiC fiber composite using micromechanical testing. Acta Materialia, 2019, 168: 178. DOI URL
[92]	JIANG Z, CHEN D, GAO C, et al. Deformation mechanisms in reaction-bonded silicon carbide ceramics via nanoindentation and nano-scratching analysis. Materials Today Communications, 2025, 46: 112746. DOI URL
[93]	XIA L, CHEN D, CAO Y, et al. High temperature nano-indentation on the mechanical properties of Zr and Zr-Fe alloys: experimental and theoretical analysis. Mechanics of Materials, 2021, 162: 104053. DOI URL
[94]	UDAYAKUMAR A, GANESH A, RAJA S, et al. Effect of intermediate heat treatment on mechanical properties of SiC_f/SiC composites with BN interphase prepared by ICVI. Journal of the European Ceramic Society, 2011, 31(6): 1145.
[95]	REBILLAT F, LAMON J, NASLAIN R, et al. Interfacial bond strength in SiC/C/SiC composite materials, as studied by single-fiber push-out tests. Journal of the American Ceramic Society, 1998, 81(4): 965.
[96]	BUET E, SAUDER C, SORNIN D, et al. Influence of surface fibre properties and textural organization of a pyrocarbon interphase on the interfacial shear stress of SiC/SiC minicomposites reinforced with Hi-Nicalon S and Tyranno SA 3 fibres. Journal of the European Ceramic Society, 2014, 34(2): 179.
[97]	YU H, ZHOU X, ZHANG W, et al. Mechanical behavior of SiC_f/SiC composites with alternating PyC/SiC multilayer interphases. Materials & Design, 2013, 44: 320. DOI URL
[98]	ZHANG L, REN C, ZHOU C, et al. Single fiber push-out characterization of interfacial mechanical properties in unidirectional CVI-C/SiC composites by the nano-indentation technique. Applied Surface Science, 2015, 357: 1427. DOI URL
[99]	LEIDE A, MARTINEZ A, CLARK G, et al. Progress towards a micro fibre push-out method for measuring fibre-matrix interface properties in SiC composites. Journal of the European Ceramic Society, 2025, 45(16): 117624.
[100]	REBILLAT F, LAMON J, GUETTE A. The concept of a strong interface applied to SiC/SiC composites with a BN interphase. Acta Materialia, 2000, 48(18/19): 4609.
[101]	MUELLER W, MOOSBURGER J, SAUSE M, et al. Microscopic analysis of single-fiber push-out tests on ceramic matrix composites performed with Berkovich and flat-end indenter and evaluation of interfacial fracture toughness. Journal of the European Ceramic Society, 2013, 33(2): 441.
[102]	RODRíGUEZ M, MOLINA J, GONZÁLEZ C, et al. A methodology to measure the interface shear strength by means of the fiber push-in test. Composites Science and Technology, 2012, 72(15): 1924.
[103]	YANG L, LIU H, CHENG H. Processing-temperature dependent micro-and macro-mechanical properties of SiC fiber reinforced SiC matrix composites. Composites Part B: Engineering, 2017, 129: 152. DOI URL
[104]	KHARRAT M, CHATEAUMINOIS A, CARPENTIER L, et al. On the interfacial behaviour of a glass/epoxy composite during a micro-indentation test: assessment of interfacial shear strength using reduced indentation curves. Composites Part A: Applied Science and Manufacturing, 2012, 28(1): 39.
[105]	GUTIERREZ G, BERNARD C, BILLAUD P, et al. The JANNuS-Saclay platform: new developments for the understanding of evolutions under irradiation in materials. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2024, 557: 165541. DOI URL
[106]	LANG E, HECKMAN N, CLARK T, et al. Development of an in situ ion irradiation scanning electron microscope. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2023, 537: 29. DOI URL
[107]	ARADI E, LEWIS J, GREAVES G, et al. In situ TEM investigations of the microstructural changes and radiation tolerance in SiC nanowhiskers irradiated with He ions at high temperatures. Acta Materialia, 2021, 210: 116820. DOI URL
[108]	KABEL J, HOSEMANN P, ZAYACHUK Y, et al. Ceramic composites: a review of toughening mechanisms and demonstration of micropillar compression for interface property extraction. Journal of Materials Research, 2018, 33(4): 424.
[109]	ZHANG L, LIN H, SUN Z, et al. Investigation of in-situ microstructural mechanical properties and thermal damage mechanisms of SiC_f/SiC under CVI and PIP processes. Materials Characterization, 2025, 220: 114689. DOI URL
[110]	SHIH C, KATOH Y, LEONARD K J, et al. Determination of interfacial mechanical properties of ceramic composites by the compression of micro-pillar test specimens. Journal of Materials Science, 2013, 48(15): 5219.
[111]	KABEL J, YANG Y, BALOOCH M, et al. Micro-mechanical evaluation of SiC-SiC composite interphase properties and debond mechanisms. Composites Part B: Engineering, 2017, 131: 173. DOI URL
[112]	KARAKOC O, KOYANAGI T, NOZAWA T, et al. Fiber/matrix debonding evaluation of SiC_f/SiC composites using micropillar compression technique. Composites Part B: Engineering, 2021, 224: 109189. DOI URL
[113]	NOZAWA T, KATOH Y, SNEAD L. The effects of neutron irradiation on shear properties of monolayered PyC and multilayered PyC/SiC interfaces of SiC/SiC composites. Journal of Nuclear Materials, 2007, 367: 685.
[114]	NOZAWA T, KATOH Y, SNEAD L. The effect of neutron irradiation on the fiber/matrix interphase of silicon carbide composites. Journal of Nuclear Materials, 2009, 384(3): 195.
[115]	BEST J P, WEHRS J, POLYAKOV M, et al. High temperature fracture toughness of ceramic coatings evaluated using micro-pillar splitting. Scripta Materialia, 2019, 162: 190. DOI URL
[116]	AST J, TIAN C, HERRE P, et al. Interfacial fracture behavior and adhesive strength in tensile and shear loading of SiC-PyC-SiC composites by micro-scale specimens. Acta Materialia, 2023, 259: 119273. DOI URL
[117]	JIMENEZ S, LEGUILLON D. Finite fracture mechanics at the micro-scale. Application to bending tests of micro cantilever beams. Engineering Fracture Mechanics, 2021, 258: 108012. DOI URL
[118]	HENRY R, ZACHARIE I, BLAY T, et al. Fracture properties of an irradiated PWR UO₂ fuel evaluated by micro-cantilever bending tests. Journal of Nuclear Materials, 2020, 538: 152209. DOI URL
[119]	FRAZER D, ABAD M, KRUMWIEDE D, et al. Localized mechanical property assessment of SiC/SiC composite materials. Composites Part A: Applied Science and Manufacturing, 2015, 70: 93. DOI URL
[120]	TATAMI J, IMOTO Y, YAHAGI T, et al. Relationship between bending strength of bulk porous silicon carbide ceramics and grain boundary strength measured using microcantilever beam specimens. Journal of the European Ceramic Society, 2020, 40(7): 2634.
[121]	ARREGUI J, KOYANAGI T, CAKMAK E, et al. Qualitative and quantitative analysis of neutron irradiation effects in SiC/SiC composites using X-ray computed tomography. Composites Part B: Engineering, 2022, 238: 109896. DOI URL
[122]	SHIBAYAMA T, MATSUO G, HAMADA K, et al. In-situ observation of fracture behavior on nano structure in NITE SiC/SiC composite by HVEM// IOP Conference Series:Materials Science and Engineering. IOP Publishing, 2011, 18(16): 162013.
[123]	MIYASHITA Y, KANDA K, ZHU S, et al. Observations of fatigue damage process in SiC/SiC composites at room and elevated temperatures. International Journal of Fatigue, 2002, 24(2/4): 241.
[124]	ZHAO S, YANG Z, ZHOU X. Fracture behavior of SiC/SiC composites with different interfaces. Journal of Inorganic Materials, 2016, 31(1): 58.
[125]	HAN D, YE F, CHENG L, et al. Matrix cracking of 2D SiC/SiC composite characterized by in situ SEM and nano-CT. Ceramics International, 2023, 49(8): 12508.
[126]	WANG L, WANG Z, DONG S, et al. Finite element simulation of stress distribution and development of C_f/SiC ceramic-matrix composite coated with single layer SiC coating during thermal shock. Composites Part B: Engineering, 2013, 51: 204. DOI URL
[127]	LI L, SONG Y, SUN Y. Modeling the tensile behavior of unidirectional C/SiC ceramic-matrix composites. Mechanics of Composite Materials, 2014, 49(6): 659.
[128]	MEYER P, WAAS A. FEM predictions of damage in continous fiber ceramic matrix composites under transverse tension using the crack band method. Acta Materialia, 2016, 102: 292. DOI URL
[129]	VAJARI D, GONZÁLEZ C, LLORCA J, et al. A numerical study of the influence of microvoids in the transverse mechanical response of unidirectional composites. Composites Science and Technology, 2014, 97: 46. DOI URL
[130]	VAJARI D. A micromechanical study of porous composites under longitudinal shear and transverse normal loading. Composite Structures, 2015, 125: 266. DOI URL
[131]	TANG J, ZHAO G, WANG J, et al. Computational geometry-based 3D yarn path modeling of wound SiC_f/SiC-cladding tubes and its application to meso-scale finite element model. Frontiers in Materials, 2021, 8: 701205. DOI URL
[132]	SHEN L, YAN W, ZHU T, et al. Analysis of multi-scale failure behavior of SiC_f/SiC composite clad tube under flexible clamping damage. Journal of the European Ceramic Society, 2024, 44(11): 6269.
[133]	FENG Y, WANG J, SHANG N, et al. Multiscale modeling of SiC_f/SiC nuclear fuel cladding based on FE-simulation of braiding process. Frontiers in Materials, 2021, 7: 634112. DOI URL
[134]	XIE F, CHEN Z, QIAO Z, et al. An asymmetric 2D braiding strategy for balancing hoop and axial strength in SiC/SiC composite nuclear fuel cladding. Composites Part B: Engineering, 2025, 308: 113013. DOI URL
[135]	XUE J, WANG S, CHEN Z, et al. A multiscale model for the thermomechanical behavior of SiC composite cladding subjected to thermo-mechanical irradiation coupling. Journal of Nuclear Materials, 2025, 615: 155948. DOI URL
[136]	CHEN B, NIU L, CHAI J, et al. Experimental investigation of microstructure and mechanical properties of β-SiC with various sintering additives supplemented by first-principles calculations. Ceramics International, 2025, 51(11): 14746.
[137]	LI Y, XIAO W, LI H. Molecular dynamics simulation of C/Si ratio effect on the irradiation swelling of β-SiC. Journal of Nuclear Materials, 2016, 480: 75. DOI URL
[138]	WANG J, CHEN L, LU Z, et al. Modeling of the damage and fracture behaviors of a SiC triplex tube during the burst test with elastomeric insert. Journal of Nuclear Materials, 2025, 603: 155420. DOI URL
[139]	RHO H, LEE Y. Development of a 2D axisymmetric SiC cladding mechanical model and its applications for steady-state and LBLOCA analysis. Journal of Nuclear Materials, 2022, 558: 153311. DOI URL
[140]	LEE Y, KAZIMI M S. A structural model for multi-layered ceramic cylinders and its application to silicon carbide cladding of light water reactor fuel. Journal of Nuclear Materials, 2015, 458: 87. DOI URL
[141]	AVINCOLA V A, GUENOUN P, SHIRVAN K. Mechanical performance of SiC three-layer cladding in PWRs. Nuclear Engineering and Design, 2016, 310: 280. DOI URL
[142]	HU C. Experimental and theoretical investigation of SiC/SiC composites under multiaxial loading. University of Minnesota, 2023.

核用SiC复合包壳多尺度力学损伤研究方法评述

Multi-scale Methods for Investigating Mechanical Damage in Nuclear SiC Composite Cladding: A Review

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