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

Autor: David E.J. Armstrong, Ruqing Xu, Suchandrima Das, Nicholas W. Phillips, Hongbing Yu, Felix Hofmann, Abdallah Reza, Kay Song, Kenichiro Mizohata
Přispěvatelé: Materials Physics
Rok vydání: 2020
Předmět:
Materials science
nanoindentation
Polymers and Plastics
LOOPS
thermal diffusivity
THIN-FOILS
Population
FOS: Physical sciences
FeCr alloys
02 engineering and technology
DIFFRACTION
THRESHOLD DISPLACEMENT ENERGIES
Thermal diffusivity
01 natural sciences
7. Clean energy
Ion
0103 physical sciences
lattice strain
STRUCTURAL-MATERIALS
Irradiation
Composite material
ion-irradiation
education
010302 applied physics
Condensed Matter - Materials Science
education.field_of_study
Metals and Alloys
Materials Science (cond-mat.mtrl-sci)
MECHANICAL-PROPERTIES
Nanoindentation
021001 nanoscience & nanotechnology
Electronic
Optical and Magnetic Materials
TEMPERATURE-DEPENDENCE
Transmission electron microscopy
216 Materials engineering
DAMAGE EVOLUTION
X-ray crystallography
Ceramics and Composites
CR MODEL ALLOYS
0210 nano-technology
Material properties
Zdroj: Acta Materialia
ISSN: 1359-6454
DOI: 10.1016/j.actamat.2020.10.015
Popis: 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.
Databáze: OpenAIRE
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