Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungsten
Tungsten (W), as the most promising candidate for plasma-facing materials, will experience significant irradiation hardening in nuclear fusion environment, which is originated from the formation of displacement damages, such as voids and dislocation loops. Hydrogen (H) can further exacerbate the har...
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| Format: | Article |
| Language: | English |
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IOP Publishing
2025-01-01
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| Series: | Nuclear Fusion |
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| Online Access: | https://doi.org/10.1088/1741-4326/ada812 |
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| author | Qing-Yuan Ren Yu-Hao Li Yu-Chen Du Tian-Ren Yang Dmitry Terentyev Wei-Zhong Han Hong-Bo Zhou Guang-Hong Lu |
| author_facet | Qing-Yuan Ren Yu-Hao Li Yu-Chen Du Tian-Ren Yang Dmitry Terentyev Wei-Zhong Han Hong-Bo Zhou Guang-Hong Lu |
| author_sort | Qing-Yuan Ren |
| collection | DOAJ |
| description | Tungsten (W), as the most promising candidate for plasma-facing materials, will experience significant irradiation hardening in nuclear fusion environment, which is originated from the formation of displacement damages, such as voids and dislocation loops. Hydrogen (H) can further exacerbate the hardening effect, but the underlying physical mechanisms remain unclear. Using molecular dynamics simulations, we investigate the impact of H aggregation within voids and ½ <111> dislocation loops on obstructing the glide of ½ <111> edge dislocations. On the one hand, the pinning effect of H-void complexes is closely related to the ratio of H to vacancy (H:Vac). When the H:Vac ratio is high, H atoms will overflow from the H-void complexes along the dislocation, enhancing the attractive interaction of complexes with dislocation and thereby causing a significant increase in the critical resolved shear stress (CRSS). On the other hand, the accumulation of H around dislocation loops can increase the CRSS by an order of magnitude. This is mainly because the binding of H to the dislocation loop hinders its movement along with the edge dislocation. Our findings advocate that the presence of interstitial impurities can dramatically modify the mechanical properties of materials underirradiation, and provide an important reference for the prediction of W performance and the development of advanced nuclear materials. |
| format | Article |
| id | doaj-art-bad9732702fc46e98601d49856e6304c |
| institution | Kabale University |
| issn | 0029-5515 |
| language | English |
| publishDate | 2025-01-01 |
| publisher | IOP Publishing |
| record_format | Article |
| series | Nuclear Fusion |
| spelling | doaj-art-bad9732702fc46e98601d49856e6304c2025-01-21T10:14:49ZengIOP PublishingNuclear Fusion0029-55152025-01-0165202604410.1088/1741-4326/ada812Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungstenQing-Yuan Ren0Yu-Hao Li1Yu-Chen Du2Tian-Ren Yang3https://orcid.org/0000-0002-1616-6115Dmitry Terentyev4Wei-Zhong Han5Hong-Bo Zhou6https://orcid.org/0000-0001-5585-6154Guang-Hong Lu7Department of Physics, Beihang University , Beijing 100191, China; Beijing Key Laboratory of Advanced Nuclear Materials and Physics, Beihang University , Beijing 100191, China; Department of Mathematics and Physics, North China Electric Power University , Baoding 071003, ChinaDepartment of Physics, Beihang University , Beijing 100191, China; Beijing Key Laboratory of Advanced Nuclear Materials and Physics, Beihang University , Beijing 100191, ChinaDepartment of Physics, Beihang University , Beijing 100191, China; Beijing Key Laboratory of Advanced Nuclear Materials and Physics, Beihang University , Beijing 100191, ChinaDepartment of Physics, Beihang University , Beijing 100191, China; Beijing Key Laboratory of Advanced Nuclear Materials and Physics, Beihang University , Beijing 100191, ChinaBelgium Nuclear Research Center , NMS unit, Boeretang 200, B2400 Mol, BelgiumCenter for Advancing Materials Performance from the Nanoscale, State Key Laboratory for Mechanical Behavior of Materials, Xi’an Jiaotong University , Xi’an 710049, ChinaDepartment of Physics, Beihang University , Beijing 100191, China; Beijing Key Laboratory of Advanced Nuclear Materials and Physics, Beihang University , Beijing 100191, ChinaDepartment of Physics, Beihang University , Beijing 100191, China; Beijing Key Laboratory of Advanced Nuclear Materials and Physics, Beihang University , Beijing 100191, ChinaTungsten (W), as the most promising candidate for plasma-facing materials, will experience significant irradiation hardening in nuclear fusion environment, which is originated from the formation of displacement damages, such as voids and dislocation loops. Hydrogen (H) can further exacerbate the hardening effect, but the underlying physical mechanisms remain unclear. Using molecular dynamics simulations, we investigate the impact of H aggregation within voids and ½ <111> dislocation loops on obstructing the glide of ½ <111> edge dislocations. On the one hand, the pinning effect of H-void complexes is closely related to the ratio of H to vacancy (H:Vac). When the H:Vac ratio is high, H atoms will overflow from the H-void complexes along the dislocation, enhancing the attractive interaction of complexes with dislocation and thereby causing a significant increase in the critical resolved shear stress (CRSS). On the other hand, the accumulation of H around dislocation loops can increase the CRSS by an order of magnitude. This is mainly because the binding of H to the dislocation loop hinders its movement along with the edge dislocation. Our findings advocate that the presence of interstitial impurities can dramatically modify the mechanical properties of materials underirradiation, and provide an important reference for the prediction of W performance and the development of advanced nuclear materials.https://doi.org/10.1088/1741-4326/ada812H aggregationvoidsdislocation loopsedge dislocation glidingcritical resolved shear stressirradiation hardening |
| spellingShingle | Qing-Yuan Ren Yu-Hao Li Yu-Chen Du Tian-Ren Yang Dmitry Terentyev Wei-Zhong Han Hong-Bo Zhou Guang-Hong Lu Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungsten Nuclear Fusion H aggregation voids dislocation loops edge dislocation gliding critical resolved shear stress irradiation hardening |
| title | Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungsten |
| title_full | Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungsten |
| title_fullStr | Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungsten |
| title_full_unstemmed | Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungsten |
| title_short | Unveiling the inhibitory effect of hydrogen-decorated voids and dislocation loops on the glide of edge dislocation in tungsten |
| title_sort | unveiling the inhibitory effect of hydrogen decorated voids and dislocation loops on the glide of edge dislocation in tungsten |
| topic | H aggregation voids dislocation loops edge dislocation gliding critical resolved shear stress irradiation hardening |
| url | https://doi.org/10.1088/1741-4326/ada812 |
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