Characterising Ion-Irradiated FeCr: Hardness, Thermal Diffusivity and Lattice Strain

Song, Kay; Das, Suchandrima; Reza, Abdallah; Phillips, Nicholas W.; Xu, Ruqing; Yu, Hongibing; Mizohata, Kenichiro; Armstrong, D. E.J.; Hofmann, Felix

doi:10.1016/j.actamat.2020.10.015

Title: Characterising Ion-Irradiated FeCr: Hardness, Thermal Diffusivity and Lattice Strain

Journal Article · Tue Dec 01 00:00:00 EST 2020 · Acta Materialia

DOI:https://doi.org/10.1016/j.actamat.2020.10.015· OSTI ID:1844349

Song, Kay; Das, Suchandrima; Reza, Abdallah; Phillips, Nicholas W.; Xu, Ruqing; Yu, Hongibing; Mizohata, Kenichiro; Armstrong, D. E.J.; Hofmann, Felix

Ion-irradiated FeCr alloys are useful for understanding and predicting neutron damage in the structural steels of future nuclear reactors. Previous studies have largely focused on the structure of irradiation induced defects, probed by transmission electron microscopy (TEM), as well as changes in mechanical properties. Across these studies, a wide range of irradiation conditions has been employed on samples with different processing histories, which complicates the analysis of the relationship between defect structures and material properties. Furthermore, key properties, such as irradiation-induced changes in thermal transport and lattice strain, are little explored. Here we present a systematic study of Fe3Cr, Fe5Cr and Fe10Cr binary alloys implanted with 20 MeV Fe3+ ions to nominal doses of 0.01 dpa and 0.1 dpa at room temperature. Nanoindentation, transient grating spectroscopy (TGS) and X-ray micro-beam Laue diffraction were used to study the changes in hardness, thermal diffusivity and strain in the material as a function of damage and Cr content. Our results suggest that Cr leads to an increased retention of irradiation-induced defects, causing substantial changes in hardness and lattice strain. However, thermal diffusivity varies little with increasing damage and instead degrades significantly with increasing Cr content in the material. We find significant lattice strains even in samples exposed to a nominal displacement damage of 0.01 dpa. The defect density predicted from the lattice strain measurements is significantly higher than that observed in previous TEM studies, suggesting that TEM may not fully capture the irradiation-induced defect population. (C) 2020 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.

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Research Organization:: Argonne National Lab. (ANL), Argonne, IL (United States)

Sponsoring Organization:: Leverhulme Trust; European Research Council (ERC); European Union - Horizon 2020 Research and Innovation Programme; Engineering and Physical Sciences Research Council (EPSRC); USDOE Office of Science - Office of Basic Energy Sciences - Scientific User Facilities Division

DOE Contract Number:: AC02-06CH11357

OSTI ID:: 1844349

Journal Information:: Acta Materialia, Vol. 201

Country of Publication:: United States

Language:: English

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Title: Characterising Ion-Irradiated FeCr: Hardness, Thermal Diffusivity and Lattice Strain

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