Selection of fuel cladding material for nuclear fission reactors

CRF Azevedo - Engineering Failure Analysis, 2011 - Elsevier
The growing understanding of the link between carbon emissions and global warming has
been promoting a discussion on the environmental and safety viability of nuclear power …

Irradiation performance of high entropy ceramics: A comprehensive comparison with conventional ceramics and high entropy alloys

S Huang, J Zhang, H Fu, Y Xiong, S Ma, X Xiang… - Progress in Materials …, 2024 - Elsevier
High entropy ceramics (HECs) are a novel class of ceramics that exhibit high melting point,
excellent high-temperature mechanical performance, and superb corrosion resistance …

Irradiation damage in (Zr0. 25Ta0. 25Nb0. 25Ti0. 25) C high-entropy carbide ceramics

F Wang, X Yan, T Wang, Y Wu, L Shao, M Nastasi, Y Lu… - Acta Materialia, 2020 - Elsevier
This research revealed the mechanisms of irradiation damage in the novel high entropy
ceramic materials.(Zr 0.25 Ta 0.25 Nb 0.25 Ti 0.25) C high-entropy carbide ceramics …

Properties of zirconium carbide for nuclear fuel applications

Y Katoh, G Vasudevamurthy, T Nozawa… - Journal of Nuclear …, 2013 - Elsevier
Zirconium carbide (ZrC) is a potential coating, oxygen-gettering, or inert matrix material for
advanced high temperature reactor fuels. ZrC has demonstrated attractive properties for …

High temperature ion irradiation effects in MAX phase ceramics

DW Clark, SJ Zinkle, MK Patel, CM Parish - Acta Materialia, 2016 - Elsevier
The family of layered carbides and nitrides known as MAX phase ceramics combine many
attractive properties of both ceramics and metals due to their nanolaminate crystal structure …

Microstructural damage evolution of (WTiVNbTa) C5 high-entropy carbide ceramics induced by self-ions irradiation

Y Zhu, J Chai, Z Wang, T Shen, L Niu, S Li, P Jin… - Journal of the European …, 2022 - Elsevier
High-entropy carbide ceramics (WTiVNbTa) C 5 were prepared by spark plasma sintering
and irradiated with 1.0 MeV C-ions at room temperature (RT) and 650℃. Irradiation induced …

Response of structure and mechanical properties of high entropy pyrochlore to heavy ion irradiation

L Xu, M Niu, H Wang, L Su, H Gao, L Zhuang - Journal of the European …, 2022 - Elsevier
Material with superior damage tolerance, chemical durability, and structure stability is of
increasing interest in high-level radioactive waste management and structural components …

A comparative study of low energy radiation responses of SiC, TiC and ZrC

M Jiang, HY Xiao, HB Zhang, SM Peng, CH Xu, ZJ Liu… - Acta Materialia, 2016 - Elsevier
In this study, an ab initio molecular dynamics method is employed to compare the responses
of SiC, TiC and ZrC to low energy irradiation. It reveals that C displacements are dominant in …

Effects of fast neutron irradiation on zirconium carbide

LL Snead, Y Katoh, S Kondo - Journal of nuclear materials, 2010 - Elsevier
High-purity zone refined zirconium carbide has been fast neutron irradiated in the dose and
temperature range of 1–10× 1025N/m2 (E> 0.1 MeV) and 635–1480° C, respectively. Non …

Helium induced microstructure damage, nano-scale grain formation and helium retention behaviour of ZrC

S Agarwal, A Bhattacharya, P Trocellier, SJ Zinkle - Acta Materialia, 2019 - Elsevier
Transition-metal ultra-high temperature ceramics are promising materials for nuclear
structural applications. However, an understanding of their response to high-temperature …