One-dimensional migration of interstitial clusters in SUS316L and its model alloys under electron irradiation-Reference-Cited by-同舟云学术

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One-dimensional migration of interstitial clusters in SUS316L and its model alloys under electron irradiation

Published:2012-03-21 Issue:9 Volume:92 Page:1129-1148
ISSN:1478-6435
Container-title:Philosophical Magazine
language:en
Short-container-title:Philosophical Magazine

Author:

Satoh Y.,Abe H.,Kim S.W.

Publisher

Informa UK Limited

Subject

Condensed Matter Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/14786435.2011.642318

Reference25 articles.

1. Primary damage formation in bcc iron

2. Dislocation loop structure, energy and mobility of self-interstitial atom clusters in bcc iron

3. Migration kinetics of the self-interstitial atom and its clusters in bcc Fe

4. One-dimensional atomic transport by clusters of self-interstitial atoms in iron and copper

5. Defect interaction processes controlling the accumulation of defects produced by high energy recoils

Cited by 16 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Effect of ion flux on one-dimensional migration of dislocation loops in Fe9Cr1.5W0.4Si F/M steel during in-situ Fe+ irradiation;Journal of Nuclear Materials;2023-06

2. Complete characterization of sink-strengths for mutually 1D-mobile defect clusters: Extension to diffusion anisotropy analog cases;Journal of Nuclear Materials;2022-12

3. In-situ observation of damage structure in Cu-Cr-Zr and Cu-Cr alloy during 1.25 MeV electron irradiation;Nuclear Materials and Energy;2022-03

4. The evolution of dislocation loop and its interaction with pre-existing dislocation in He+-irradiated molybdenum: in-situ TEM observation and molecular dynamics simulation;Acta Materialia;2020-12

5. Effect of confinement of SIA cluster diffusion by impurities on radiation defect accumulation due to 14 MeV neutrons in tungsten;Journal of Nuclear Materials;2020-12

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