Dependence of irradiation defects evolution on dose rate and PKA energy spectrum in tungsten
• Higher dose rates promote the nucleation of irradiation defects, leading to a substantial increase in defect density and a decrease in defect size. • A modified predictive model is proposed to characterize the compensatory effect of temperature on different dose rates. • Differently, the influence of PKA energy spectrum cannot be compensated by temperature variation. Heavy-ion irradiation is considered as an effective method to study the performance of nuclear materials under neutron irradiation, while these two types of experiments show the striking difference in microstructure evolution and thermo-mechanical properties. In this work, taking tungsten (W) as an example, we systematically investigated how dose rate and primary knock-on atom (PKA) energy spectrum affect the evolution of displacement damages in materials using object kinetic Monte Carlo (OKMC) method. It is found that the increase of dose rate promotes the nucleation of vacancy clusters and dislocation loops but inhibits their growth, which is in agreement with the experimental results. This should be attributed to shortened evolution time, which suppresses the migration and dissociation of defects and promotes their nucleation, which can be compensated by the increase of temperature. Accordingly, a modified predictive model has been proposed to characterize the compensatory effect of temperature on different dose rates. However, different from the dose rate, the influence of PKA energy spectrum cannot be compensated by temperature variation, because the high-energy PKAs may generate large and stable defect clusters directly during collision cascade. These results clarify the influence of dose rate and PKA energy spectrum on the evolution of displacement defects in W, and provide valuable insights for assessing the performance of materials under neutron irradiation.
Authors
- D. Terentyev (ORCID: https://orcid.org/0000-0002-1138-9803)
- Hong-Bo Zhou (ORCID: https://orcid.org/0000-0001-5585-6154)
- Wei Zhao (ORCID: https://orcid.org/0000-0001-7177-3180)
- Hui-Zhi Ma
- Yu‐Hao Li (ORCID: https://orcid.org/0000-0003-1839-0900)
- Zhangcan Yang (ORCID: https://orcid.org/0000-0002-5621-6789)
- Guang-Hong Lü (ORCID: https://orcid.org/0000-0002-3039-1706)
- Yu-Ze Niu
Institutions
- Belgian Nuclear Research Centre (BE)
- Huazhong University of Science and Technology (CN)
- Beihang University (CN)
Publication Details
- Journal
- Nuclear Materials and Energy
- Published
- 2025-05-26
- DOI
- https://doi.org/10.1016/j.nme.2025.101956
- Primary Topic
- Fusion materials and technologies
- Type
- article
- Field-Weighted Citation Impact
- 0.00
Funders
- National Natural Science Foundation of China
- Fundamental Research Funds for the Central Universities