A multiscale model for the thermomechanical behavior of SiC composite cladding subjected to thermo-mechanical irradiation coupling
文献类型：期刊论文
| 作者 | Xue, Jiaxiang3; Wang, Shihuai3; Chen, Zhaoke2; Yang ZM(杨正茂)1
|
| 刊名 | JOURNAL OF NUCLEAR MATERIALS
 |
| 出版日期 | 2025-09-01 |
| 卷号 | 615页码:12 |
| 关键词 | SiC composite cladding SiC/SiC composites Non-linear constitutive model Swelling Thermo-mechanical analysis |
| ISSN号 | 0022-3115 |
| DOI | 10.1016/j.jnucmat.2025.155948 |
| 通讯作者 | Chen, Zhaoke(chenzhaoke2008@csu.edu.cn) ; Yang, Zhengmao(zmyang@imech.ac.cn) |
| 英文摘要 | Silicon carbide (SiC) composite cladding serves as the primary safety barrier against nuclear leakage in advanced nuclear reactors, playing a critical role in accident-tolerant fuel. However, its structural integrity under coupled thermo-mechanical-irradiation conditions remains a significant challenge, one that is not yet fully understood. This study establishes a hierarchical multiscale framework to investigate the synergistic damage mechanisms that govern SiC composite claddings subjected to extreme temperature gradients, neutron irradiation, and mechanical loads. At the mesoscale, a non-orthogonal, curved representative volume element (RVE) with explicit fiber tows-matrix-interphase architecture is developed using a novel coordinate mapping strategy. This approach effectively resolves the geometric complexities inherent in tubular woven composites while maintaining topological consistency. At the macroscale, a thermodynamically consistent continuum damage mechanics model is formulated, incorporating irradiation-induced swelling, anisotropic creep, and thermal strain interactions through nonlinear constitutive relations. The framework uniquely integrates micromechanical interactions (such as matrix cracking and interfacial debonding) with radiation physics, where defect-driven thermal resistivity degradation and stiffness reduction are dynamically coupled through homogenized material properties derived from RVE asymptotics. The results indicate that the proposed framework provides a comprehensive description of the microscopic damage mechanisms in SiC composite cladding, and can be used for future hierarchical multiscale analyses of SiC composite cladding systems. |
| 分类号 | 一类 |
| WOS关键词 | MATRIX COMPOSITES ; SILICON-CARBIDE ; CREEP ; FIBER ; TUBE |
| 资助项目 | National Natural Science Foundation of China (NSFC)[U24B2028] ; National Natural Science Foundation of China (NSFC)[52105165] |
| WOS研究方向 | Materials Science ; Nuclear Science & Technology |
| 语种 | 英语 |
| WOS记录号 | WOS:001514223500003 |
| 资助机构 | National Natural Science Foundation of China (NSFC) |
| 其他责任者 | Chen, Zhaoke，杨正茂 |
| 源URL | [http://dspace.imech.ac.cn/handle/311007/101889]  |
| 专题 | 宽域飞行工程科学与应用中心 |
| 作者单位 | 1.Chinese Acad Sci, Inst Mech, Beijing 100190, Peoples R China 2.Cent South Univ, State Key Lab Powder Met, Changsha 410083, Peoples R China; 3.China Nucl Power Technol Res Inst, Nucl Fuel & Mat Dept, Shenzhen 518026, Peoples R China; |
| 推荐引用方式 GB/T 7714 | Xue, Jiaxiang,Wang, Shihuai,Chen, Zhaoke,et al. A multiscale model for the thermomechanical behavior of SiC composite cladding subjected to thermo-mechanical irradiation coupling[J]. JOURNAL OF NUCLEAR MATERIALS,2025,615:12. |
| APA | Xue, Jiaxiang,Wang, Shihuai,Chen, Zhaoke,&杨正茂.(2025).A multiscale model for the thermomechanical behavior of SiC composite cladding subjected to thermo-mechanical irradiation coupling.JOURNAL OF NUCLEAR MATERIALS,615,12. |
| MLA | Xue, Jiaxiang,et al."A multiscale model for the thermomechanical behavior of SiC composite cladding subjected to thermo-mechanical irradiation coupling".JOURNAL OF NUCLEAR MATERIALS 615(2025):12. |
入库方式： OAI收割
来源：力学研究所
浏览0
下载0
收藏0
其他版本
除非特别说明，本系统中所有内容都受版权保护，并保留所有权利。