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Main Authors: Song, Kay, Sheyfer, Dina, Mizohata, Kenichiro, Zhang, Minyi, Liu, Wenjun, Gürsoy, Doğa, Yang, David, Tolkachev, Ivan, Yu, Hongbing, Armstrong, David E J, Hofmann, Felix
Format: Preprint
Published: 2023
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Online Access:https://arxiv.org/abs/2308.00771
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author Song, Kay
Sheyfer, Dina
Mizohata, Kenichiro
Zhang, Minyi
Liu, Wenjun
Gürsoy, Doğa
Yang, David
Tolkachev, Ivan
Yu, Hongbing
Armstrong, David E J
Hofmann, Felix
author_facet Song, Kay
Sheyfer, Dina
Mizohata, Kenichiro
Zhang, Minyi
Liu, Wenjun
Gürsoy, Doğa
Yang, David
Tolkachev, Ivan
Yu, Hongbing
Armstrong, David E J
Hofmann, Felix
contents Ferritic/martensitic steels will be used as structural components in next generation nuclear reactors. Their successful operation relies on an understanding of irradiation-induced defect behaviour in the material. In this study, Fe and FeCr alloys (3-12%Cr) were irradiated with 20 MeV Fe-ions at 313 K to doses ranging between 0.00008 dpa to 6.0 dpa. This dose range covers six orders of magnitude, spanning low, transition and high dose regimes. Lattice strain and hardness in the irradiated material were characterised with micro-beam Laue X-ray diffraction and nanoindentation, respectively. Irradiation hardening was observed even at very low doses (0.00008 dpa) and showed a monotonic increase with dose up to 6.0 dpa. Lattice strain measurements of samples at 0.0008 dpa allow the calculation of equivalent Frenkel pair densities and corrections to the Norgett-Robinson-Torrens (NRT) model for Fe and FeCr alloys at low dose. NRT efficiency for FeCr is 0.2, which agrees with literature values for high irradiation energy. Lattice strain increases up to 0.8 dpa and then decreases when the damage dose is further increased. The strains measured in this study are lower and peak at a larger dose than predicted by atomistic simulations. This difference can be explained by taking temperature and impurities into account.
format Preprint
id arxiv_https___arxiv_org_abs_2308_00771
institution arXiv
publishDate 2023
record_format arxiv
spellingShingle Dose and compositional dependence of irradiation-induced property change in FeCr
Song, Kay
Sheyfer, Dina
Mizohata, Kenichiro
Zhang, Minyi
Liu, Wenjun
Gürsoy, Doğa
Yang, David
Tolkachev, Ivan
Yu, Hongbing
Armstrong, David E J
Hofmann, Felix
Materials Science
Ferritic/martensitic steels will be used as structural components in next generation nuclear reactors. Their successful operation relies on an understanding of irradiation-induced defect behaviour in the material. In this study, Fe and FeCr alloys (3-12%Cr) were irradiated with 20 MeV Fe-ions at 313 K to doses ranging between 0.00008 dpa to 6.0 dpa. This dose range covers six orders of magnitude, spanning low, transition and high dose regimes. Lattice strain and hardness in the irradiated material were characterised with micro-beam Laue X-ray diffraction and nanoindentation, respectively. Irradiation hardening was observed even at very low doses (0.00008 dpa) and showed a monotonic increase with dose up to 6.0 dpa. Lattice strain measurements of samples at 0.0008 dpa allow the calculation of equivalent Frenkel pair densities and corrections to the Norgett-Robinson-Torrens (NRT) model for Fe and FeCr alloys at low dose. NRT efficiency for FeCr is 0.2, which agrees with literature values for high irradiation energy. Lattice strain increases up to 0.8 dpa and then decreases when the damage dose is further increased. The strains measured in this study are lower and peak at a larger dose than predicted by atomistic simulations. This difference can be explained by taking temperature and impurities into account.
title Dose and compositional dependence of irradiation-induced property change in FeCr
topic Materials Science
url https://arxiv.org/abs/2308.00771