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Part A: Materials Science

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

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Pages 1129-1148 | Received 18 Aug 2010, Accepted 14 Nov 2011, Published online: 03 Jan 2012

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Read on this site (4)

Y. Satoh, H. Abe, Y. Matsukawa, T. Matsunaga, S. Kano, S. Arai, Y. Yamamoto & N. Tanaka. (2015) One-dimensional migration of interstitial clusters in SUS316L and its model alloys at elevated temperatures. Philosophical Magazine 95:14, pages 1587-1606.
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Y. Satoh, H. Abe & T. Matsunaga. (2014) Radiation-induced glide motion of interstitial clusters in concentrated alloys. Philosophical Magazine 94:19, pages 2170-2187.
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M. Horiki, T. Yoshiie, K. Sato & Q. Xu. (2013) Point defect processes in neutron irradiated Ni, Fe–15Cr–16Ni and Ti-added modified SUS316SS. Philosophical Magazine 93:14, pages 1701-1714.
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Y. Satoh, H. Abe & T. Matsunaga. (2013) Modeling of fluctuating interaction energy between a gliding interstitial cluster and solute atoms in random binary alloys. Philosophical Magazine 93:14, pages 1652-1676.
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Articles from other publishers (11)

Gang Yang, Yukun Wu, Yifan Ding, Yipeng Li, Ziqi Cao, Gang Li, Dewang Cui, Kun He, Xi Qiu & Guang Ran. (2023) 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 579, pages 154412.
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Gilles Adjanor. (2022) Complete characterization of sink-strengths for mutually 1D-mobile defect clusters: Extension to diffusion anisotropy analog cases. Journal of Nuclear Materials 572, pages 153970.
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M. Hatakeyama, T. Yamamoto, K. Yasuda, S. Matsumura, K. Yasunaga & K. Sato. (2022) In-situ observation of damage structure in Cu-Cr-Zr and Cu-Cr alloy during 1.25 MeV electron irradiation. Nuclear Materials and Energy 30, pages 101144.
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Giridhar Nandipati, Wahyu Setyawan, Kenneth J. Roche, Richard J. Kurtz & Brian D. Wirth. (2020) Effect of confinement of SIA cluster diffusion by impurities on radiation defect accumulation due to 14 MeV neutrons in tungsten. Journal of Nuclear Materials 542, pages 152402.
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Yipeng Li, Guang Ran, Yijia Guo, Zhipeng Sun, Xinyi Liu, Yuanming Li, Xi Qiu & Yong Xin. (2020) 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 201, pages 462-476.
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Dongyue Chen, Kenta Murakami, Hiroaki Abe, Zhengcao Li & Naoto Sekimura. (2019) Investigation of interactions between defect clusters in stainless steels by in situ irradiation at elevated temperatures. Acta Materialia 163, pages 78-90.
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B. Michaut, T. Jourdan, J. Malaplate, A. Renault-Laborne, F. Sefta & B. Décamps. (2017) Cluster dynamics modeling and experimental investigation of the effect of injected interstitials. Journal of Nuclear Materials 496, pages 166-176.
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K. Sato, Q. Xu & T. Yoshiie. (2017) Simulation of the effect of volume size factor of solute atoms and their clusters on one dimensional motion of interstitial clusters in Ni binary alloys. Computational Materials Science 132, pages 1-5.
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Giridhar Nandipati, Wahyu Setyawan, Howard L. Heinisch, Kenneth J. Roche, Richard J. Kurtz & Brian D. Wirth. (2015) Displacement cascades and defect annealing in tungsten, Part III: The sensitivity of cascade annealing in tungsten to the values of kinetic parameters. Journal of Nuclear Materials 462, pages 345-353.
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Kotaro Ono, Mitsutaka Miyamoto, Kazuto Arakawa, Shin-ichi Matsumoto & Fumiaki Kudo. (2014) Effects of precipitated helium, deuterium or alloy elements on glissile motion of dislocation loops in Fe–9Cr–2W ferritic alloy. Journal of Nuclear Materials 455:1-3, pages 162-166.
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K. Ono, M. Miyamoto & F. Kudo. (2014) Release of deuterium from irradiation damage in Fe?9Cr?2W ferritic alloy irradiated with deuterium ions. Journal of Nuclear Materials 452:1-3, pages 46-50.
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