Irradiation effects in high-entropy alloys and their applications
Z Cheng, J Sun, X Gao, Y Wang, J Cui, T Wang… - Journal of Alloys and …, 2023 - Elsevier
On the one hand, Irradiation is everywhere and irradiation effect, especially the material
irradiation damage effect under strong irradiation field, is one of the key factors for the …
irradiation damage effect under strong irradiation field, is one of the key factors for the …
Interactions between edge dislocation and irradiation dislocation loop in BCC refractory high entropy alloys and the lattice distortion effect on irradiation hardening …
J Li, Y Zhu, L Zhao, S Liang, M Huang, Z Li - Journal of Alloys and …, 2024 - Elsevier
The irradiation resistance of body-centered cubic (BCC) refractory high entropy alloys
(RHEAs) has been relatively less studied compared with face-centered cubic (FCC) …
(RHEAs) has been relatively less studied compared with face-centered cubic (FCC) …
Pinning of extended dislocations in atomically disordered crystals
In recent years there has been renewed interest in the behavior of dislocations in crystals
that exhibit strong atomic scale disorder, as typical of compositionally complex single phase …
that exhibit strong atomic scale disorder, as typical of compositionally complex single phase …
The effect of grain boundary on irradiation resistance of CoCrCuFeNi high entropy alloy
Defect traps have been well known to influence the irradiation resistance of traditional
structural materials, but to what extent is not fully clear for high entropy alloys. Herein, the …
structural materials, but to what extent is not fully clear for high entropy alloys. Herein, the …
Uniaxial tensile behaviors and Hall-Petch relationship of polycrystalline 316LN stainless steel via molecular dynamics simulation
C Hong, YH Lu, HB Zheng, ZH Li, GJ Guo - Computational Materials …, 2024 - Elsevier
A molecular dynamics (MD) simulation method was used to investigate the effects of
element position, tensile strain rate (ε ̇) and average grain diameter (d) on the uniaxial …
element position, tensile strain rate (ε ̇) and average grain diameter (d) on the uniaxial …
The preexisting edge dislocations as recombination center of point defects enhancing irradiation tolerance in CoCrCuFeNi high entropy alloy
Y Liu, R Li, Q Peng - Materialia, 2022 - Elsevier
Defect clusters including dislocations, grain boundaries, and precipitations can serve as sink
sources for point defects during radiation damage. As a result, radiation tolerance can be …
sources for point defects during radiation damage. As a result, radiation tolerance can be …
Advances in Understanding the Evolution Mechanism of Micropore Defects in Metal Materials under External Loads
J Liang, M Zhang, Y Peng, J Wang - Metals, 2024 - mdpi.com
Micropores are one of the critical factors affecting materials' performance and service life. As
the need for a deeper understanding of micropore evolution and damage mechanisms …
the need for a deeper understanding of micropore evolution and damage mechanisms …
A microstructure-based study of irradiation hardening in stainless steel: Experiment and phase field modeling
D Wang, L Zhao, L Xu, Y Han, K Hao - Journal of Nuclear Materials, 2022 - Elsevier
Irradiation hardening plays an important role in the mechanical property and service lifetime
of structural materials in nuclear power plants. The irradiation hardening of irradiated 316H …
of structural materials in nuclear power plants. The irradiation hardening of irradiated 316H …
Comparative analysis of irradiation-stimulated hardening in the austenite and ferrite phases of F321 stainless steel
P Lin, J Nie, W Cui, L He, S Cui, Y Lu - Acta Materialia, 2024 - Elsevier
F321 stainless steel is renowned for its outstanding mechanical properties and corrosion
resistance, making it a crucial structural material in light water reactors and high-temperature …
resistance, making it a crucial structural material in light water reactors and high-temperature …
The statistic and fluctuant phenomena of interaction between edge extended dislocation and microvoid in FCC CoCrFeCuNi high entropy alloy
Irradiation induced microvoids in nuclear-service materials can act as obstacles for
dislocation glide and thus change the mechanical behavior of irradiated materials. High …
dislocation glide and thus change the mechanical behavior of irradiated materials. High …