Effects of irradiation temperature and dose rate on the mechanical properties of self-ion implanted Fe and Fe–Cr alloys

Hardie, Christopher D.; Williams, Ceri A.; Xu, Shuo; Roberts, Steve

doi:10.1016/j.jnucmat.2013.03.052

Cited by 122 publications

(45 citation statements)

References 36 publications

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“…Firstly, the higher ion damage dose rate may lead to significantly faster accumulation of damage by ions compared to neutrons, altering the nucleation and growth of the clusters. Such effects have been observed in binary FeCr alloys [39]. Secondly, the total irradiation time in the neutron irradiation is significantly longer, thus allowing more time for diffusion to operate and promoting enrichment of clusters into discrete precipitates.…”

Section: Irradiation Hardeningmentioning

confidence: 91%

Ion-irradiation-induced clustering in W–Re and W–Re–Os alloys: A comparative study using atom probe tomography and nanoindentation measurements

et al. 2015

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This study examines clustering and hardening in W-2 at.% Re and W-1 at.% Re-1 at.% Os alloys induced by 2 MeV W + ion irradiation at 573 and 773 K. Such clusters are known precursors to the formation of embrittling precipitates, a potentially life-limiting phenomenon in the operation of fusion reactor components. Increases in hardness were studied using nanoindentation. The presence of osmium significantly increased postirradiation hardening. Atom probe tomography analysis revealed clustering in both alloys, with the size and number densities strongly dependent on alloy composition and irradiation temperature. The highest cluster number density was found in the ternary alloy irradiated at 773 K. In the ternary alloy, Os was found to cluster preferentially compared to Re. The implications of this result for the structural integrity of fusion reactor components are discussed. Crown

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Section: Irradiation Hardeningmentioning

confidence: 91%

Ion-irradiation-induced clustering in W–Re and W–Re–Os alloys: A comparative study using atom probe tomography and nanoindentation measurements

et al. 2015

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“…In contrast, there are few methods available for the characterisation of mechanical properties from such small volumes of material, and analyses regarding best practise and validity of using these techniques for irradiated materials are scarce. There have been several investigations which have used nanoindentation as a means to measure the effects of ion irradiation on mechanical properties [1][2][3][4][5][6][7][8][9][10][11][12]. The majority of investigations have been conducted using a Berkovich tip geometry and include various methods such as load-unload [1,2] and continuous stiffness measurement (CSM) [8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

Understanding the effects of ion irradiation using nanoindentation techniques

Hardie

Roberts

Bushby

2015

Journal of Nuclear Materials

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The effects of ion irradiation in materials for research are usually limited to a shallow surface layer of the order of one micrometre in depth. Determining the mechanical properties of such irradiated materials requires techniques with high spatial resolution. Nanoindentation is a relatively simple method for investigating these shallow layers with the advantage that statistically rich data sets for elastic and plastic property values can be generated. However, interpretation of the results requires and understanding of the material response, including the extent of the plastic zone with respect to the irradiated layer, pile-up or sink-in of material around the indentation site that affect the calculated contact area and hence derived mechanical property values. An Fe + self-irradiated Fe12%Cr alloy was investigated with three different indenter tip geometries, a Cube corner, Berkovich and 10 micron radius indenter. Sharp indenters provide sufficiently small plastic zones to be contained within the irradiated layer but pop-in events and pile-up need to be taken into account for correct interpretation of the mechanical properties of the irradiated material.

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“…In alloys, including alloys formed due to transmutation nuclear reactions [3], chemical segregation also occurs, resulting in the formation of helium bubbles [4][5][6], chromium or rhenium precipitates [7,8], and giving rise to grain boundary embrittlement [3,9]. Interpreting the observed microstructural evolution effects requires extending the measure of radiation damage beyond the displacement per atom (dpa) concept, proposed by Norgett et al [10] to quantify the exposure of materials to fluxes of energetic particles [11].…”

mentioning

confidence: 99%

Subcascade formation and defect cluster size scaling in high-energy collision events in metals

Backer¹,

Sand²,

Nordlund³

et al. 2016

EPL

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Az -Theory and Models of Radiation Effects PACS 61.82.Bg -Metals and Alloys PACS 61.72.J--Point Defects and Defect clustersAbstract -Recently, a scaling law describing the formation of defect clusters under irradiation has been established [1,2]. A critical constraint associated with its application to phenomena occurring over a broad range of irradiation conditions is the limitation on the energy of incident particles. Incident neutrons or ions, with energies exceeding a certain energy threshold, produce a complex hierarchy of collision subcascade events, which impedes the use of the defect cluster size scaling law derived for an individual low-energy cascade. By analyzing the statistics of subcascade sizes and energies, we show that defect clustering above threshold energies can be described by a product of two scaling laws, one for the sizes of subcascades and the other for the sizes of defect clusters formed in subcascades. The statistics of subcascade sizes exhibits a transition at a threshold energy, where the subcascade morphology changes from a single molten domain below the energy threshold, to several or many molten sub-domains above the threshold. The number of sub-domains then increases in proportion to the primary knock-on atom energy. The model has been validated against direct molecular dynamics simulations and applied to W, Fe, Be, Zr and sixteen other metals, enabling the prediction of full statistics of defect cluster sizes with no limitation on the energy of cascade events. We find that populations of defect clusters produced by the fragmented high-energy cascades are dominated by individual Frenkel pairs and relatively small defect clusters, whereas the lower-energy non-fragmented cascades produce a greater proportion of large defect clusters.

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Effects of irradiation temperature and dose rate on the mechanical properties of self-ion implanted Fe and Fe–Cr alloys

Cited by 122 publications

References 36 publications

Ion-irradiation-induced clustering in W–Re and W–Re–Os alloys: A comparative study using atom probe tomography and nanoindentation measurements

Ion-irradiation-induced clustering in W–Re and W–Re–Os alloys: A comparative study using atom probe tomography and nanoindentation measurements

Understanding the effects of ion irradiation using nanoindentation techniques

Subcascade formation and defect cluster size scaling in high-energy collision events in metals

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