4.7 Article

Effect of Weibull parameters and crack distribution on the failure probability of multi-layered SiC cladding

Related references

Note: Only part of the references are listed.
Article Nuclear Science & Technology

Effect of initial coating crack on the mechanical performance of surface-coated zircaloy cladding

Ze Xu et al.

Summary: This paper investigates the mechanical performance of cracked surface-coated Zircaloy cladding under different conditions. The study focuses on stress field near the crack tip and energy release rate to determine the safety, discussion, and danger zones of initial crack lengths. The conclusions provide reference and guidance for the cladding design of nuclear fuel elements.

NUCLEAR ENGINEERING AND TECHNOLOGY (2021)

Article Materials Science, Multidisciplinary

Hydrothermal Corrosion of First-Generation Dual-Purpose Coatings on Silicon Carbide for Accident-Tolerant Fuel Cladding

Peter J. Doyle et al.

Summary: Four different commercial coatings were deposited on high resistivity SiC for corrosion mitigation and fission gas hermeticity testing. The Cr/CrN coating quickly spalled, while the CrN coating preferentially spalled in oxygenated conditions. TiN coatings fully oxidized and spalled, but all coatings were chemically stable in hydrogen. Localized spallation was identified as a common issue across all coatings. Future improvements are recommended for better protection.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Materials Science, Multidisciplinary

Damage mechanics modeling of the non-linear behavior of SiC/SiC ceramic matrix composite fuel cladding

Mohammad Alabdullah et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

Article Materials Science, Multidisciplinary

Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response

Yangbin Deng et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Materials Science, Multidisciplinary

Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis

Gyanender Singh et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

Review Materials Science, Multidisciplinary

Accident tolerant fuel cladding development: Promise, status, and challenges

Kurt A. Terrani

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Nuclear Science & Technology

Failure probability analysis and design comparison of multi-layered SiC-based fuel cladding in PWRs

Tao Zhang et al.

NUCLEAR ENGINEERING AND DESIGN (2018)

Article Materials Science, Ceramics

Hydrothermal corrosion behavior of SiCf/SiC composites candidate for PWR accident tolerant fuel cladding

Hong Yang et al.

CERAMICS INTERNATIONAL (2018)

Article Materials Science, Ceramics

Thermal shock resistance and hoop strength of triplex silicon carbide composite tubes

Daejong Kim et al.

INTERNATIONAL JOURNAL OF APPLIED CERAMIC TECHNOLOGY (2017)

Article Nuclear Science & Technology

Design optimization of multi-layer Silicon Carbide cladding for light water reactors

Youho Lee et al.

NUCLEAR ENGINEERING AND DESIGN (2017)

Article Nuclear Science & Technology

Mechanical performance of SiC three-layer cladding in PWRs

Valentina Angelici Avincola et al.

NUCLEAR ENGINEERING AND DESIGN (2016)

Article Materials Science, Multidisciplinary

Characterization of SiC-SiC composites for accident tolerant fuel cladding

C. P. Deck et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

Article Materials Science, Multidisciplinary

Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding

J. G. Stone et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

Article Nuclear Science & Technology

Failure probabilities of SiC clad fuel during a LOCA in public acceptable simple SMR (PASS)

Youho Lee et al.

NUCLEAR ENGINEERING AND DESIGN (2015)

Article Materials Science, Multidisciplinary

Accident tolerant fuels for LWRs: A perspective

S. J. Zinkle et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Multidisciplinary

Thermo-mechanical analysis of LWR SiC/SiC composite cladding

M. Ben-Belgacem et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

Article Materials Science, Ceramics

Silicon Carbide Oxidation in Steam up to 2 MPa

Kurt A. Terrani et al.

JOURNAL OF THE AMERICAN CERAMIC SOCIETY (2014)

Article Nuclear Science & Technology

Determination and prediction of axial/off-axial mechanical properties of SiC/SiC composites

Takashi Nozawa et al.

FUSION ENGINEERING AND DESIGN (2012)

Article Materials Science, Multidisciplinary

Stability of SiC and its composites at high neutron fluence

Yutai Katoh et al.

JOURNAL OF NUCLEAR MATERIALS (2011)

Article Materials Science, Multidisciplinary

Evaluation of neutron irradiated silicon carbide and silicon carbide composites

George Newsome et al.

JOURNAL OF NUCLEAR MATERIALS (2007)

Article Materials Science, Multidisciplinary

Handbook of SiC properties for fuel performance modeling

Lance L. Snead et al.

JOURNAL OF NUCLEAR MATERIALS (2007)

Article Nuclear Science & Technology

Progress in blanket designs using SiCf/SiC composites

L Giancarli et al.

FUSION ENGINEERING AND DESIGN (2002)