A reduced cluster dynamics modeling of radiation damage in tungsten

• A reduced cluster dynamics model is developed to study the evolution of helium bubbles and interstitial loops. • The model includes an atomically informed loop punching mechanism for bubble growth. • Predicted loop and void/bubble densities, sizes agree with experimental data. • At lower temperatures, voids/bubbles do not form in irradiated tungsten. • Loop punching significantly affects bubble pressure and helium-to-vacancy ratio. A reduced cluster dynamics model is developed to investigate the microstructure evolution of irradiated single crystal tungsten. The model accounts for the generation and reaction of point defects, small-size defect clusters, helium clusters, as well as the nucleation and growth of large immobile defects, including the interstitial dislocation loops, voids and helium bubbles. Moreover, by incorporating an atomically informed loop punching mechanism for bubble growth, the model is able to accurately capture the evolution kinetics of radiation-induced defects with and without the helium implantation. The predicted densities and sizes of loops and voids/bubbles, the helium-to-vacancy ratio and the internal pressure of helium bubbles are all in good agreement with experimental data at different irradiation doses across a wide range of temperatures from 300 K up to 1200 K. This work aims to provide a robust tool for analyzing the microstructure of irradiated tungsten under both fission and fusion conditions.

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Publication Details

Journal
Nuclear Materials and Energy
Published
2024-11-13
DOI
https://doi.org/10.1016/j.nme.2024.101814
Citations
1
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.12

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article

A reduced cluster dynamics modeling of radiation damage in tungsten

Tenglong Cong, Gui-Jun Ding, Yang Li, Pengchuang Liu et al.
1 citations
Nuclear Materials and Energy
Fusion materials and technologies
0.12
article

A reduced cluster dynamics modeling of radiation damage in tungsten

Tenglong Cong, Gui-Jun Ding, Yang Li, Pengchuang Liu, Zhiyuan Li
article en
1 citations

Abstract

• A reduced cluster dynamics model is developed to study the evolution of helium bubbles and interstitial loops. • The model includes an atomically informed loop punching mechanism for bubble growth. • Predicted loop and void/bubble densities, sizes agree with experimental data. • At lower temperatures, voids/bubbles do not form in irradiated tungsten. • Loop punching significantly affects bubble pressure and helium-to-vacancy ratio. A reduced cluster dynamics model is developed to investigate the microstructure evolution of irradiated single crystal tungsten. The model accounts for the generation and reaction of point defects, small-size defect clusters, helium clusters, as well as the nucleation and growth of large immobile defects, including the interstitial dislocation loops, voids and helium bubbles. Moreover, by incorporating an atomically informed loop punching mechanism for bubble growth, the model is able to accurately capture the evolution kinetics of radiation-induced defects with and without the helium implantation. The predicted densities and sizes of loops and voids/bubbles, the helium-to-vacancy ratio and the internal pressure of helium bubbles are all in good agreement with experimental data at different irradiation doses across a wide range of temperatures from 300 K up to 1200 K. This work aims to provide a robust tool for analyzing the microstructure of irradiated tungsten under both fission and fusion conditions.

Nuclear Materials and EnergyVol. 41
Shanghai University (CN), Commercial Aircraft Corporation of China (China) (CN), Shanghai Jiao Tong University (CN), Science and Technology on Surface Physics and Chemistry Laboratory (CN)
National Natural Science Foundation of China, Science and Technology on Surface Physics and Chemistry Laboratory
Openalex Percentile: Top 58%
Fusion materials and technologies
0.12
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