Development and Application of a Mechanical Model for Multilayer Anisotropic Cladding

Zhang Ruixiao; He Yanan; Wu Yingwei; Tian Wenxi; Qiu Suizheng; Su Guanghui

doi:10.13832/j.jnpe.2024.S1.0110

Volume 45 Issue S1

Jun. 2024

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2024 > 45(S1): 110-116

Zhang Ruixiao, He Yanan, Wu Yingwei, Tian Wenxi, Qiu Suizheng, Su Guanghui. Development and Application of a Mechanical Model for Multilayer Anisotropic Cladding[J]. Nuclear Power Engineering, 2024, 45(S1): 110-116. doi: 10.13832/j.jnpe.2024.S1.0110

Citation:

Zhang Ruixiao, He Yanan, Wu Yingwei, Tian Wenxi, Qiu Suizheng, Su Guanghui. Development and Application of a Mechanical Model for Multilayer Anisotropic Cladding[J]. Nuclear Power Engineering, 2024, 45(S1): 110-116. doi: 10.13832/j.jnpe.2024.S1.0110

Citation:

PDF( 6563 KB)

Development and Application of a Mechanical Model for Multilayer Anisotropic Cladding

doi: 10.13832/j.jnpe.2024.S1.0110

State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China

Received Date: 2023-12-28
Rev Recd Date: 2024-04-24
Publish Date: 2024-06-15

Abstract

Abstract

The multilayer SiC composites cladding composed of monolithic SiC and SiC fiber/matrix composite (SiC_f/SiC) is a popular choice for accident-tolerant fuel cladding. However, typical fuel performance analysis codes currently lack the modeling capability for the anisotropic mechanical behavior of SiC_f/SiC materials. In order to enhance the precision of mechanical calculations for composite SiC cladding in fuel performance analysis, a mechanical model was developed for multilayer anisotropic materials and integrated into the fuel performance analysis code FRAPCON4.0. Validation of the model's accuracy was conducted using a multilayer SiC cladding thermal-mechanical coupling case. The mechanical calculation capability for SiC composite cladding with orthotropic mechanical properties and multiaxial pseudoplastic behavior was achieved, and the performance of duplex-layer SiC cladding fuel elements under normal operation condition was analyzed. The developed mechanical model in this study is adaptable to arbitrary multilayer cylindrical structure fuel elements and has the capability to analyze orthotropic mechanical parameters and behaviors, rendering it applicable to various types of novel fuel element analyses.
- SiC cladding,
- Accident tolerant fuel (ATF),
- Pellet-cladding mechanical interaction (PCMI),
- Anisotropic material

FullText(HTML)

References(13)

References

[1]	TERRANI K A. Accident tolerant fuel cladding development: promise, status, and challenges[J]. Journal of Nuclear Materials, 2018, 501: 13-30.
[2]	KATOH Y, OZAWA K, SHIH C, et al. Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: properties and irradiation effects[J]. Journal of Nuclear Materials, 2014, 448(1-3): 448-476.
[3]	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[J]. Journal of Nuclear Materials, 2015, 458: 87-105.
[4]	KATOH Y, SNEAD L L. Silicon carbide and its composites for nuclear applications - Historical overview[J]. Journal of Nuclear Materials, 2019, 526: 151849.
[5]	SNEAD L L, NOZAWA T, KATOH Y, et al. Handbook of SiC properties for fuel performance modeling[J]. Journal of Nuclear Materials, 2007, 371(1-3): 329-377.
[6]	KATOH Y, NOZAWA T, SNEAD L L, et al. Stability of SiC and its composites at high neutron fluence[J]. Journal of Nuclear Materials, 2011, 417(1-3): 400-405.
[7]	SUKJAI Y. Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors[D]. Cambridge: Massachusetts Institute of Technology, 2014.
[8]	BEN-BELGACEM M, RICHET V, TERRANI K A, et al. Thermo-mechanical analysis of LWR SiC/SiC composite cladding[J]. Journal of Nuclear Materials, 2014, 447(1-3): 125-142.
[9]	DENG Y B, SHIRVAN K, WU Y W, et al. Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response[J]. Journal of Nuclear Materials, 2018, 507: 24-37.
[10]	RHO H, LEE Y. Development of a 2D axisymmetric SiC cladding mechanical model and its applications for steady-state and LBLOCA analysis[J]. Journal of Nuclear Materials, 2022, 558: 153311.
[11]	邓阳斌,贺亚男,巫英伟,等. 多层结构包壳和非刚体芯块力学建模及应用[J]. 原子能科学技术,2018, 52(7): 1308-1315. doi: 10.7538/yzk.2017.youxian.0611
[12]	DENG Y B, WU Y W, QIU B W, et al. Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs[J]. Annals of Nuclear Energy, 2017, 104: 146-156.
[13]	HE Y N, SHIRVAN K, WU Y W, et al. Fuel performance optimization of U₃Si₂-SiC design during normal, power ramp and RIA conditions[J]. Nuclear Engineering and Design, 2019, 353: 110276.