Nature and thermal stability of radiation defects in single-crystal tungsten

Bykov, V. N.; Birzhevoi, G. A.; Zakharova, M. I.; Соловьев, В. А.

doi:10.1007/bf01666749

Cited by 14 publications

(13 citation statements)

References 11 publications

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“…Stage II, between À170°C and 350°C, is a steady recovery attributed to the release of interstitials from traps with a wide range of interaction energies from 0.25 to 1.7 eV [27]. This explains the many sub-stages observed for example in resistivity studies [17]. These two stages occur below fusion reactor operating temperatures, and will not be considered further here.…”

Section: Previous Recovery Studiesmentioning

confidence: 95%

“…Numerous studies have also been undertaken with regard to the recovery of irradiation-induced defects post-irradiation. However, these have mostly centred around resistivity measurements [12][13][14][15][16][17][18][19], with some early field ion microscopy work [20,21] and a single early TEM study on single crystal tungsten [22]. A similar TEM work has also been done in molybdenum [23].…”

Section: Previous Recovery Studiesmentioning

confidence: 96%

“…In single-crystal tungsten, 2 defects were found to be stable up to 1900°C, [17] presumably due to the absence of sinks at grain boundaries. Bykov et al [17] identified three stages of annealing: 500-800 (Stage IV), 950-1200 (Stage V), and 1200-1900 (Stage VI).…”

Section: Previous Recovery Studiesmentioning

confidence: 97%

“…Stage IV recovery, at 0:22T m , is still subject to debate [14], being generally attributed to vacancy-impurity complexes [33], or di-vacancies [17]. Recent DFT simulations have shown that di-vacancies are not favoured in tungsten [34].…”

Section: Previous Recovery Studiesmentioning

confidence: 98%

“…Higher temperature recovery stages in tungsten have been largely un-researched since the 1970s, with interpretation being limited to resistivity measurements and early FIM experiments [17,33,20].…”

Section: Previous Recovery Studiesmentioning

confidence: 99%

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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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Section: Previous Recovery Studiesmentioning

confidence: 95%

Section: Previous Recovery Studiesmentioning

confidence: 96%

Section: Previous Recovery Studiesmentioning

confidence: 97%

Section: Previous Recovery Studiesmentioning

confidence: 98%

Section: Previous Recovery Studiesmentioning

confidence: 99%

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High temperature annealing of ion irradiated tungsten

et al. 2015

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Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations

et al. 2015

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The displacement damage induced in W and W-5 wt.% Re and W-5 wt.% Ta alloys by 2 MeV W + irradiation to doses 3.3×10 17-2.5×10 19 W + /m 2 at temperatures ranging from 300 to 750°C has been characterized by transmission electron microscopy. An automated sizing and counting approach based on Image J (a Java-based image processing program developed at the National Institutes of Health) [1] has been performed for all near-bulk irradiation data. In all cases the damage comprised dislocation loops, mostly of interstitial type, with Burgers vectors b = ½<111> (> 60%) and b = <100>. The diameters of loops did not exceed 20 nm with most being ≤ 6 nm diameter. The loop number density varied between 10 22 and 10 23 loops/m 3. With increasing irradiation temperature, the loop size distributions shifted towards larger sizes, and there was a substantial decrease in loop number densities. The damage microstructure was less sensitive to dose than to temperature. Under the same irradiation conditions, loop number densities in the W-Re and W-Ta alloys were higher than in pure W but loops were smaller. In grains with normals close to z = <001>, loop strings developed in pure W at temperatures ≥ 500°C and doses ≥ 1.2 dpa, but such strings were not observed in the W-Re or W-Ta alloys. However, in other grain orientations complex structures appeared in all materials and dense dislocation networks formed at higher doses.

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Thermal diffusivity recovery and defect annealing kinetics of self-ion implanted tungsten probed by insitu transient grating spectroscopy

Reza

Dennett

et al. 2022

Acta Materialia

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Nature and thermal stability of radiation defects in single-crystal tungsten

Cited by 14 publications

References 11 publications

High temperature annealing of ion irradiated tungsten

High temperature annealing of ion irradiated tungsten

Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations

Thermal diffusivity recovery and defect annealing kinetics of self-ion implanted tungsten probed by insitu transient grating spectroscopy

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