The effect of low energy helium ion irradiation on tungsten-tantalum (W-Ta) alloys under fusion relevant conditions

Gonderman, S.; Tripathi, J.; Novakowski, T.J.; Sizyuk, T.; Hassanein, A.

doi:10.1016/j.jnucmat.2017.05.009

Cited by 41 publications

(21 citation statements)

References 33 publications

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“…The study involves pure W (99.95 purity; Alfa Aesar) hereafter W, and W-Ta alloy (5 wt.% Ta, American Elements) hereafter W-5Ta. Details of W-Ta alloying procedure were described elsewhere in previous studies [32]. In situ x-ray photoelectron spectroscopy (XPS) and electron backscattering diffraction (EBSD) studies on virgin samples were performed to verify the stoichiometry of each sample type [32] and to get the information about the average grain size and their distributions.…”

Section: Tungsten Samples and Sample Preparationmentioning

confidence: 99%

“…Details of W-Ta alloying procedure were described elsewhere in previous studies [32]. In situ x-ray photoelectron spectroscopy (XPS) and electron backscattering diffraction (EBSD) studies on virgin samples were performed to verify the stoichiometry of each sample type [32] and to get the information about the average grain size and their distributions. Figure 1 is an EBSD viewgraph depicting the average grain size and orientation of W (figure 1(a)) and W-5Ta (figure 1(b)) samples.…”

Section: Tungsten Samples and Sample Preparationmentioning

confidence: 99%

“…Perhaps the most interesting improvement of W-Ta alloys is their response to low energy, He + and D + ion irradiation induced surface deterioration. Several studies have shown W-Ta alloys exhibit a significant reduction in hydrogen (H) isotope retention in response to low energy D + ion irradiation [29][30][31], as well as resistance to fuzz formation in response to low energy He + ion irradiation [32].…”

Section: Introductionmentioning

confidence: 99%

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Suppression of surface microstructure evolution in W and W–Ta alloys during simultaneous and sequential He and D ion irradiation in fusion relevant conditions

et al. 2017

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Tungsten (W) has been selected as the divertor material in ITER based on its promising thermal and mechanical properties. Despite these advantages, continued investigation has revealed W to undergo extreme surface morphology evolution in response to relevant fusion operating conditions. These complications spur the need for further exploration of W and other innovative plasma facing components (PFCs) for future fusion devices. Recent literature has shown that alloying of W with other refractory metals, such as tantalum (Ta), results in the enhancement of key PFC properties including, but not limited to, ductility, hydrogen isotope retention, and helium ion (He + ) radiation tolerance. In the present study, pure W and W-Ta alloys are exposed to simultaneous and sequential low energy, He + and deuterium (D + ) ion beam irradiations at high (1223 K) and low (523 K) temperatures. The goal of this study is to cultivate a complete understanding of the synergistic effects induced by dual and sequential ion irradiation on W and W-Ta alloy surface morphology evolution. For the dual ion beam experiments, W and W-Ta samples were subjected to four different He + : D + ion ratios (100% He + , 60% D + + 40% He + , 90% D + + 10% He + and 100% D + ) having a total constant He + fluence of 6 × 10 24 ion m −2 . The W and W-Ta samples both exhibit the expected damaged surfaces under the 100% He + irradiation, but as the ratio of D + / He + ions increases there is a clear suppression of the surface morphology at high temperatures. This observation is supported by the sequential experiments, which show a similar suppression of surface morphology when W and W-Ta samples are first exposed to low energy He + irradiation and then exposed to subsequent low energy D + irradiation at high temperatures. Interestingly, this morphology suppression is not observed at low temperatures, implying there is a D-W interaction mechanism which is dependent on temperature that is driving the suppression of the microstructure evolution in both the pure W and W-Ta alloys. Minor irradiation tolerance enhancement in the performance of the W-Ta samples is also observed.

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Section: Tungsten Samples and Sample Preparationmentioning

confidence: 99%

Section: Tungsten Samples and Sample Preparationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Suppression of surface microstructure evolution in W and W–Ta alloys during simultaneous and sequential He and D ion irradiation in fusion relevant conditions

et al. 2017

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“…W-Ti alloys have shown reduced fuzz growth when subject to He plasmas, attributed to the refined grain size [16]. W-Ta alloys have shown an increased threshold for fuzz formation [24]. W-Nb alloys have shown enhanced He bubble formation in Nb-rich regions [25], while W-5%V alloys mitigated fuzz formation compared to pure W [26].…”

Section: Introductionmentioning

confidence: 99%

Compositional Effects of Additively Manufactured Refractory High-Entropy Alloys under High-Energy Helium Irradiation

et al. 2022

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High-Entropy Alloys (HEAs) are proposed as materials for a variety of extreme environments, including both fission and fusion radiation applications. To withstand these harsh environments, materials processing must be tailored to their given application, now achieved through additive manufacturing processes. However, radiation application opportunities remain limited due to an incomplete understanding of the effects of irradiation on HEA performance. In this letter, we investigate the response of additively manufactured refractory high-entropy alloys (RHEAs) to helium (He) ion bombardment. Through analytical microscopy studies, we show the interplay between the alloy composition and the He bubble size and density to demonstrate how increasing the compositional complexity can limit the He bubble effects, but care must be taken in selecting the appropriate constituent elements.

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“…Previous studies have shown that irradiation damages can be mitigated by alloying with small amounts of additives to W. For example, W-Ta alloys not only exhibit higher ultimate tensile strength (UTS) and prevent crack propagation [15], but also suppress the formation of He bubbles [16], and fuzzes [17]. W-Re alloys are known to improve ductility [18], and effectively suppress defects formed by neutron irradiation [19].…”

Section: Introductionmentioning

confidence: 99%

Combinatorial Discovery of Irradiation Damage Tolerant Nano-structured W-based alloys

Jo¹,

Park²,

You³

et al. 2022

Preprint

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One of the challenges in fusion reactors is the discovery of plasma facing materials capable of withstanding extreme conditions, such as radiation damage and high heat flux. Development of fusion materials can be a daunting task since vast combinations of microstructures and compositions need to be explored, each of which requires trial-and-error based irradiation experiments and materials characterizations. Here, we utilize combinatorial experiments that allow rapid and systematic characterizations of composition-microstructure dependent irradiation damage behaviors of nanostructured tungsten alloys. The combinatorial materials library of W-Re-Ta alloys was synthesized, followed by the high-throughput experiments for probing irradiation damages to the mechanical, thermal, and structural properties of the alloys. This highly efficient technique allows rapid identification of composition ranges with excellent damage tolerance. We find that the distribution of implanted He clusters can be significantly altered by the addition of Ta and Re, which play a critical role in determining property changes upon irradiation.

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The effect of low energy helium ion irradiation on tungsten-tantalum (W-Ta) alloys under fusion relevant conditions

Cited by 41 publications

References 33 publications

Suppression of surface microstructure evolution in W and W–Ta alloys during simultaneous and sequential He and D ion irradiation in fusion relevant conditions

Suppression of surface microstructure evolution in W and W–Ta alloys during simultaneous and sequential He and D ion irradiation in fusion relevant conditions

Compositional Effects of Additively Manufactured Refractory High-Entropy Alloys under High-Energy Helium Irradiation

Combinatorial Discovery of Irradiation Damage Tolerant Nano-structured W-based alloys

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