Suppression of radiation-induced point defects by rhenium and osmium interstitials in tungsten

Suzudo, Tomoaki; Hasegawa, Akira

doi:10.1038/srep36738

Cited by 33 publications

(14 citation statements)

References 30 publications

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“…This is consistent with nano-indentation observations where the presence of rhenium in tungsten had no significant effect on the hardening behaviour [54]. Rather, it has been seen through DFT that presence of rhenium in tungsten actually enhances vacancy-interstitial recombination (suggested that the vacancy suppression occurs at isolated interstitials) and suppression of void swelling, leading to the idea that addition of rhenium to tungsten can improve its radiation-resistance [55]. This of course must be balanced with irradiation-induced clustering of rhenium that sets in at high damage doses and leads to substantial hardening as rhenium clusters act as efficient obstacles to dislocation motion [56][57][58].…”

Section: Average Of Measured Between 1-2 µM (× − )supporting

confidence: 84%

Helium-implantation-induced lattice strains and defects in tungsten probed by X-ray micro-diffraction

Das

Liu

et al. 2018

Materials & Design

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Tungsten is the main candidate material for plasma-facing armour components in future fusion reactors. Bombardment with energetic fusion neutrons causes collision cascade damage and defect formation. Interaction of defects with helium, produced by transmutation and injected from the plasma, modifies defect retention and behaviour. Here we investigate the residual lattice strains caused by different doses of heliumion-implantation into tungsten and tungsten-rhenium alloys. Energy and depth-resolved synchrotron X-ray micro-diffraction uniquely permits the measurement of lattice strain with sub-micron 3D spatial resolution and ~10 -4 strain sensitivity. Increase of helium dose from 300 appm to 3000 appm increases volumetric strain by only ~2.4 times, indicating that defect retention per injected helium atom is ~3 times higher at low helium doses. This suggests defect retention is not a simple function of implanted helium dose, but strongly depends on material composition and presence of impurities. Conversely, analysis of W-1wt% Re alloy samples and of different crystal orientations shows that both the presence of rhenium, and crystal orientation, have a comparatively small effect on defect retention. These insights are key for the design of armour components in future reactors where it will be essential to account for irradiation-induced dimensional change when predicting component lifetime and performance.

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Section: Average Of Measured Between 1-2 µM (× − )supporting

confidence: 84%

Helium-implantation-induced lattice strains and defects in tungsten probed by X-ray micro-diffraction

Das

Liu

et al. 2018

Materials & Design

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“…rhenium (Re) and osmium (Os) are all produced under the real irradiation conditions. These elements can significantly affect the microstructure evolution of defects and complicate the defect-GB interaction processes/mechanisms described here [46][47][48][49][50][51][52][53][54][55]. First-principles calculations by Zhou et al [46] suggest that it is energetically and kinetically favorable for the W GB of Σ5(3 1 0)/[0 0 1] to trap H coming from the bulk.…”

Section: Effects Of the H/he And Alloying Elements On The Healing Promentioning

confidence: 96%

“…First principles calculations by Suzudo et al [49] suggested that the stable configuration of alloying elements Re and Os solutes in W was a mixed dumbbell with a W atom that migrates three-dimensionally. The intrinsic SIA in W is a crowdion migrating one-dimensionally.…”

Section: Effects Of the H/he And Alloying Elements On The Healing Promentioning

confidence: 99%

Interaction of radiation-induced defects with tungsten grain boundaries at across scales: a short review

Zhang

et al. 2020

Tungsten

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As promising candidates for plasma-facing materials, tungsten-based materials suffer the irradiation of high-energy neutrons in addition to the hydrogen isotopes and helium irradiation and the high-thermal flux. Radiation-produced defects, e.g. selfinterstitial atoms (SIAs) and vacancies (Vs), can induce the hardening and embrittlement of tungsten, meanwhile enhancing the retention of hydrogen isotopes and helium in tungsten. Reducing the grain size of materials to introduce a high density of defect sinks, e.g., grain boundaries (GBs) prevalent in nano-/ultrafine-crystalline materials, was demonstrated to be an effective approach for mitigating irradiation damage in tungsten. In this paper, we reviewed the theoretical advances in exploring radiation-resistance of nano-structured tungsten at across scales. It was concentrated on the results of molecular dynamics, molecular statics, and the object kinetic Monte Carlo simulations on the fundamental interaction of the radiationcreated Vs and SIAs with the GB. These mechanisms include GB-promoted V/SIA migration and SIA-V recombination, interstitial-emission induced annihilation, coupling of the V migration close to the GB with the SIA motion within the GB, and interstitial reflection by the locally dense GB structure. We proposed the remaining scientific issues on the defect-GB interactions at across scales and their relation to experimental observations. We prospected the possible trends for simulating the radiation damage accumulation and healing processes in nano-structured tungsten in terms of the development of the across-scale computational techniques and efficiency of the GB-enhanced tolerance of tungsten to irradiation under complex in-service conditions.

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“…The W-Re binary system is less extensively studied than Fe-Cr, however, recent studies have used a similar on-lattice approach, with a DFT parameterised pairwise energy model, and solute concentration dependant interactions [19]. In W-Re, the mixed interstitial dumbbell is thought to be of particular importance, as unlike the selfinterstitial which is confined to 1D motion, the mixed interstitial is able to move through a series of rotations and translations, to effectively migrate in 3D [20][21][22]. This increased mobility of the mixed interstitial has been shown to facilitate the nucleation and growth of Re clusters in KMC models, despite the predicted solid solution.…”

Section: Introductionmentioning

confidence: 99%

Radiation-induced segregation in W-Re: from kinetic Monte Carlo simulations to atom probe tomography experiments

et al. 2019

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A viable fusion power station is reliant on the development of plasma facing materials that can withstand the combined effects of high temperature operation and high neutron doses. In this study we focus on W, the most promising candidate material. Re is the primary transmutation product and has been shown to induce embrittlement through cluster formation and precipitation below its predicted solubility limit in W. We investigate the mechanism behind this using a kinetic Monte Carlo model, implemented into Stochastic Parallel PARticle Kinetic Simulator (SPPARKS) code and parameterised with a pairwise energy model for both interstitial and vacancy type defects. By introducing point defect sinks into our simulation cell, we observe the formation of Re rich clusters which have a concentration similar to that observed in ion irradiation experiments. We also compliment our computational work with atom probe tomography (APT) of ion implanted, model W-Re alloys. The segregation of Re to grain boundaries is observed in both our APT and KMC simulations.

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Suppression of radiation-induced point defects by rhenium and osmium interstitials in tungsten

Cited by 33 publications

References 30 publications

Helium-implantation-induced lattice strains and defects in tungsten probed by X-ray micro-diffraction

Helium-implantation-induced lattice strains and defects in tungsten probed by X-ray micro-diffraction

Interaction of radiation-induced defects with tungsten grain boundaries at across scales: a short review

Radiation-induced segregation in W-Re: from kinetic Monte Carlo simulations to atom probe tomography experiments

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