4.7 Article

Primary radiation damage in tungsten-based high-entropy alloy: Interatomic potential and collision cascade simulations

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 585, Issue -, Pages -

Publisher

ELSEVIER
DOI: 10.1016/j.jnucmat.2023.154646

Keywords

Tungsten-based high-entropy alloy; Interatomic potential; Collision cascade; Radiation defects; Molecular dynamics simulations

Ask authors/readers for more resources

Tungsten-based high-entropy alloys (HEAs) have shown good properties as nuclear fusion materials. However, due to the large calculations and lack of appropriate interatomic interaction potentials, there are limited studies on collision cascades and primary radiation damage in W-based HEAs. In this study, a semi-empirical interatomic potential for W-Ta-Cr-V was developed, and molecular dynamics simulations were performed to evaluate the primary damage in W-based HEAs. The results showed that W38Ta36Cr15V11 alloy had more defect production and fewer dislocation loops compared to pure W.
Tungsten (W)-based high-entropy alloys (HEAs) have shown promising properties as nuclear fusion materials. Characterizing the primary damage is a critical step in describing and revealing the irradiation-induced damage and radiation resistance mechanism. However, there are a limited number of studies on collision cascades and primary radiation damage in W-based HEAs, owing to the large amount of calculations involved and a lack of appropriate interatomic interaction potentials. In this work, we developed a semi-empirical interatomic potential for W-Ta-Cr-V. By using the developed potential, molecular dynamics simulations of collision cascades in Wbased HEAs were performed to assess the primary damage due to irradiation. Based on experimental samples, we reported defect production in W38Ta36Cr15V11 and compared it to pure W for primary knock-on atom with energies ranging from 1 keV to 100 keV. Our findings showed that the number of FPs at the thermal spike and the number of surviving FPs at the end of the cascade in W38Ta36Cr15V11 are more than those in pure W, mainly due to the lower threshold displacement energy, melting temperature, and formation energy of point defects. Collision cascades in the W38Ta36Cr15V11 are less likely to result in the formation of dislocation loops compared to pure W. After collision cascade, in W38Ta36Cr15V11, the concentrations of Cr and V atoms in defects is significantly higher than their corresponding concentrations in the system, showing an aggregation tendency. The current collision cascade results provide insights into the primary damage of W-based HEA system under irradiation and should provide reliable guidance for describing the primary damage source terms needed in the kinetic models used to simulate radiation-induced microstructural evolution.

Authors

I am an author on this paper
Click your name to claim this paper and add it to your profile.

Reviews

Primary Rating

4.7
Not enough ratings

Secondary Ratings

Novelty
-
Significance
-
Scientific rigor
-
Rate this paper

Recommended

No Data Available
No Data Available