Hardening of self ion implanted tungsten and tungsten 5-wt% rhenium

Armstrong, David E.J.; Yi, Xiaoou; Marquis, Emmanuelle A.; Roberts, Steve

doi:10.1016/j.jnucmat.2012.07.044

Cited by 121 publications

(73 citation statements)

References 43 publications

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“…A tandem accelerator was used to irradiate the samples with 2 MeV W + ions to a fluence of 2.64 Â 10 15 ions cm À2 at a flux of 1.96 Â 10 10 ions cm À2 s À1 . A SRIM (stopping range of ions in matter) calculation predicts a damage profile extending to 300 nm below the surface, yielding an equivalent peak damage level of 33 dpa (calculated using the full cascade damage model with a binding energy of 68 eV) [15,16,18].…”

Section: Experimental Methodsmentioning

confidence: 99%

“…There are difficulties with extracting hardness values from such thin irradiated layers where there will be significant penetration of the plastic zone into the unirradiated material. The method described by Armstrong et al [15] was used to identify the region in which the hardness of the implanted layer dominates over the unimplanted layer, thus reported hardness values are taken at 125 nm indenter penetration.…”

Section: Experimental Methodsmentioning

confidence: 99%

“…They were able to determine, using 1-D atom probe mass spectrometry, that the precipitates contained either $50 or $75 at.% Re. However, the alloys they considered were of much higher Tungsten ion implantation experiments were performed on a commercial W-5 at.% Re alloy by Armstrong et al [15] from 0.04 to 33 dpa damage levels at 300°C. Atom probe tomography (APT) showed that a large increase in hardness above the 13 dpa damage level was associated with the formation of rhenium clusters $3 nm in diameter, though no study of the composition or density of these clusters was performed.…”

Section: Introductionmentioning

confidence: 99%

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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: Experimental Methodsmentioning

confidence: 99%

Section: Experimental Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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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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“…Micro-mechanical testing has been used to characterise the mechanical properties of materials for a wide range of applications, such as micro-electro-mechanical systems [8] [9], single crystal and polycrystalline silicon and silicon-based dialectic thin films [10] [11][12] [13], tungsten-based alloys for the use of plasma-facing components in future magnetic confinement fusion reactors [14], nanocrystalline metals [15], and in biomaterials to test constituent elements such as individual collagen fibrils [16]. Amongst the micro-scale approaches, nano-indentation tests provides the hardness and indentation modulus on the surface of samples; but the geometry of the elastic/inelastic zone below the indenter varies with crystal orientation and local microstructure.…”

Section: A C C E P T E D Accepted Manuscriptmentioning

confidence: 99%

Deformation and fracture of carbonaceous materials using in situ micro-mechanical testing

Liu

Flewitt

2017

Carbon

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General rightsThis document is made available in accordance with publisher policies. Please cite only the published version using the reference above. This is a PDF file of an unedited manuscript that has been accepted for publication. As a service to our customers we are providing this early version of the manuscript. The manuscript will undergo copyediting, typesetting, and review of the resulting proof before it is published in its final form. Please note that during the production process errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal pertain.Deformation and fracture of carbonaceous materials using in situ micro-mechanical testing AbstractThe local mechanical properties of vitreous carbon and another three porous graphite materials have been investigated using a novel in situ micro-cantilever bending approach.Vitreous carbon is used for validation of the micro-mechanical measurements. Filter graphite is a single phase material with ~52 vol.% porosity. Gilsocarbon graphite is a nuclear-grade graphite that is currently used in the advanced gas-cooled reactors in the UK with ~20 vol.% porosity in the filler particles and matrix; Pile Grade-A graphite (PGA) was extracted from a fuel brick within a Magnox reactor core with 15% weight loss due to neutron irradiation and CO 2 radiolytic oxidation. The 'true' material properties obtained at micro-scale are found to be of much higher value than those measured at the macro-scale due to different failure controlling mechanisms. In particular for the PGA graphite, the micro-mechanical tests allowed the mechanical properties of the filler particles and matrix to be measured separately.The filler particles showed a higher stiffness and flexural strength compared with the matrix indicating the different influence of neutron irradiation on these two constituents. It is demonstrated here that the local mechanical properties of carbonaceous materials with various complex microstructures and even following neutron irradiation can be successfully evaluated.

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“…Grains were chosen close to the h0 0 1i orientation, as samples following pre-irradiation heat treatment had a predominantly {0 0 1}h1 1 0i texture [42]. The same sample area $0.25 lm 2 was imaged near three poles, exciting a total of eight independent g-vectors in order to determine the Burgers vectors of loops, using the invisibility criterion for a prismatic dislocation loop.…”

Section: Dislocation Characterisation Proceduresmentioning

confidence: 99%

High temperature annealing of ion irradiated tungsten

et al. 2015

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Transmission electron microscopy of high temperature annealing of pure tungsten irradiated by self-ions was conducted to elucidate microstructural and defect evolution in temperature ranges relevant to fusion reactor applications (500-1200°C). Bulk isochronal and isothermal annealing of ion irradiated pure tungsten (2 MeV W + ions, 500°C, 10 14 W + /cm 2 ) with temperatures of 800, 950, 1100 and 1400°C, from 0.5 to 8 h, was followed by ex situ characterisation of defect size, number density, Burgers vector and nature. Loops with diameters larger than 2-3 nm were considered for detailed analysis, among which all loops had b ¼ 1 2 h1 1 1i and were predominantly of interstitial nature. In situ annealing experiments from 300 up to 1200°C were also carried out, including dynamic temperature ramp-ups. These confirmed an acceleration of loop loss above 900°C. At different temperatures within this range, dislocations exhibited behaviour such as initial isolated loop hopping followed by large-scale rearrangements into loop chains, coalescence and finally line-loop interactions and widespread absorption by free-surfaces at increasing temperatures. An activation energy for the annealing of dislocation length was derived, finding E a ¼ 1:34 AE 0:2 eV for the 700-1100°C range.

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Hardening of self ion implanted tungsten and tungsten 5-wt% rhenium

Cited by 121 publications

References 43 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

Deformation and fracture of carbonaceous materials using in situ micro-mechanical testing

High temperature annealing of ion irradiated tungsten

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