Multiscale modeling of SiCf/SiC nuclear fuel cladding based on FE-simulation of braiding process

Research output: Contribution to journalResearch articleContributedpeer-review

Contributors

  • Yajie Feng - , CAS - Ningbo Institute of Material Technology and Engineering (Author)
  • Jun Wang - , CAS - Ningbo Institute of Material Technology and Engineering, University of Chinese Academy of Sciences (Author)
  • Nianwei Shang - , CAS - Ningbo Institute of Material Technology and Engineering, TUD Dresden University of Technology (Author)
  • Gang Zhao - , CAS - Ningbo Institute of Material Technology and Engineering, Dalian University of Technology (Author)
  • Chao Zhang - , CAS - Ningbo Institute of Material Technology and Engineering (Author)
  • Jianbo Tang - , CAS - Ningbo Institute of Material Technology and Engineering, Shandong University (Author)
  • Shiqing Xin - , Shandong University (Author)
  • Andreas Hornig - , Institute of Lightweight Engineering and Polymer Technology (Author)
  • Maik Gude - , Chair of Lightweight Design and Structural Assessment (Author)
  • Qing Huang - , CAS - Ningbo Institute of Material Technology and Engineering, University of Chinese Academy of Sciences (Author)
  • Xigao Jian - , Dalian University of Technology (Author)
  • Jian Xu - , CAS - Ningbo Institute of Material Technology and Engineering, University of Chinese Academy of Sciences, Dalian University of Technology (Author)

Abstract

A generalized multiscale (micro-macro) finite element (FE) model for SiC-fiber reinforced SiC-matrix ceramic (SiCf/SiC) nuclear fuel claddings is established. In the macro level, the solid mesh of braided preform, which can be tailored by machine settings (braid angle, yarn width, and so on), is generated based on the braiding process simulation using the dynamic FE-solver, hiring the contact constraints. The matrix mesh and the yarn mesh are integrated by the embedded region constraint, with which the meshing difficulties can be avoided. In the micro-UD model, the progressive damage of the ceramic matrix is modeled using the phase field method (PFM) and the fracture is captured by Mohr–Coulombs criterion, which are stable and efficient in the description of the brittle crack initiation, coalition, and branching. Based on this multiscale model, the mechanical behavior of the braided SiCf/SiC nuclear fuel cladding tube is studied in detail. The superiorities over the homogenized tube model are demonstrated, too.

Details

Original languageEnglish
Article number634112
JournalFrontiers in Materials
Volume7
Publication statusPublished - 8 Feb 2021
Peer-reviewedYes

External IDs

Scopus 85101276245
ORCID /0000-0003-1370-064X/work/142243428
ORCID /0000-0003-2653-7546/work/142249308

Keywords

Keywords

  • SiCf/SiC composite, multiscale model, nuclear fuel cladding, Mohr–Coulombs criterion, phase field method, SiCf/SiC composite, nuclear fuel cladding, multiscale model