Nanoindentation study of the combined effects of crystallography, heat treatment and exposure to high-flux deuterium plasma in tungsten

Zayachuk, Y.; Armstrong, David E.J.; Bystrov, K.; Boxel, S.C.J. van; Morgan, T.W.; Roberts, Sigrid C.

doi:10.1016/j.jnucmat.2017.01.026

Cited by 22 publications

(15 citation statements)

References 34 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This study reveals highly relevant new details of the interaction between deuterium and dislocations in tungsten. The observed strain hardening agrees with previous studies [77,94,102] on tungsten. Moreover, we were also able to capture the pinning effect by deuterium-induced vacancies, which has only been experimentally reported for aluminum as measured with an environmental transmission electron microscope [41].…”

Section: Discussionsupporting

confidence: 92%

See 1 more Smart Citation

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Morgan

Terentyev

et al. 2020

Nucl. Fusion

View full text Add to dashboard Cite

DOI to the publisher's website.• The final author version and the galley proof are versions of the publication after peer review.• The final published version features the final layout of the paper including the volume, issue and page numbers. Link to publication General rightsCopyright and moral rights for the publications made accessible in the public portal are retained by the authors and/or other copyright owners and it is a condition of accessing publications that users recognise and abide by the legal requirements associated with these rights.• Users may download and print one copy of any publication from the public portal for the purpose of private study or research. • You may not further distribute the material or use it for any profit-making activity or commercial gain • You may freely distribute the URL identifying the publication in the public portal.If the publication is distributed under the terms of Article 25fa of the Dutch Copyright Act, indicated by the "Taverne" license above, please follow below link for the End User Agreement:

show abstract

Section: Discussionsupporting

confidence: 92%

“…It is worth mentioning that the pop-ins observed here are distinct from those described in [76][77][78]. In those studies, the effect of hydrogen plasma exposure on the pop-in response in tungsten was investigated, whereby it was concluded that the hydrogen plasma exposure reduces the pop-in probability.…”

Section: Stepwise Tds and Nanoindentationmentioning

confidence: 68%

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Morgan

Terentyev

et al. 2020

Nucl. Fusion

View full text Add to dashboard Cite

show abstract

“…In terms of mechanical properties, retained deuterium can bring about reduced pop-in load and increase in hardness (maximum increase of 0.5 GPa) as observed by nanoindentation of tungsten exposed to deuterium plasma at 443 K, with incident ion energy of 35 eV and accumulated fluence of 8.1 × 10 25 ions/m 2 [15]. Similar observations of increased hardness were made by Terentyev et al [115] and Zayachuk et al [116] in tungsten exposed to deuterium plasma. Overall, observations from past studies clearly indicate that despite the fast diffusion of hydrogen isotopes at fusion relevant temperatures, a significant percentage of the injected ions will be trapped by irradiation defects.…”

Section: The Effect Of Hydrogen On the Plasma-facing Componentsupporting

confidence: 70%

Recent advances in characterising irradiation damage in tungsten for fusion power

Das

2019

SN Appl. Sci.

View full text Add to dashboard Cite

Tungsten is the front-runner candidate for building the plasma-facing armour components for future fusion reactors. However, in-service irradiation by fusion-neutrons and helium will create lattice-defects in the material, compromising its properties and lifetime. Improving the component's resilience to radiation damage and accurately predicting the lifetime of irradiated components is key for commercial feasibility of the reactor. For this purpose, understanding the creation and evolution of radiation damage is essential. This paper reviews recent advances in characterising radiation damage through experimental and modelling techniques. Tungsten-ion-and helium-ion-implantation are commonly used to mimic the damage created by neutron-and helium-irradiation respectively. Defects (> 1.5 nm) can be directly imaged using transmission electron microscopy while all defects (size-independent), may be indirectly probed by measuring lattice strains induced by them (using diffraction techniques; synchrotron X-rays or high-resolution electron-backscatter). Neutron-irradiation produces mainly ½〈111〉 prismatic loops. Loop-interaction and structural organisation evolves with changing implantation dose and temperature. Helium-irradiation, < 573 K, induces formation of small helium-vacancy clusters, which evolve into bubbles, blisters and "fuzz" structure with changing temperature and dose. Nano-indentation or micro-cantilever bending tests can be used to examine mechanical properties of ion-implanted layers. Both heliumand neutron-implantation defects induce increased hardening often followed by subsequent strain-softening and localised deformation. Such irradiation-induced alterations are detrimental to material ductility and long-term structural integrity of tungsten-based components. Development of physically-based material models that capture the physics of underlying irradiation-induced changes, inspire confidence of reliably using simulations to predict mechanical behaviour and in-service performance of irradiated engineering components in future.

show abstract

“…Substantially, irradiation hardening in plasma-exposed materials has been generally ascribed to dislocations (loops) [6], bubbles or cavities [5,41] and D penetration [42], etc. However, the specific roles played by distinct damage defects on irradiation hardening are rarely reported in previous literatures.…”

Section: Discussionmentioning

confidence: 99%

“…In their following study, the mechanical properties of deuterium (D) plasma-exposed tungsten was tested by the Berkovich nano-indentation, and the surface hardening was attributed to the D deposition measured by the corresponding nuclear reaction analysis (NRA) profile [5]. Zayachuk et al [6] also suggested that the irradiation hardening after high flux D plasma exposure originated from the trapping of diffusing D atoms by dislocations in both deformed and recrystallized tungsten. In the meanwhile, H blisters, acting as the primary surface modification at the service condition [7] are also expected to be strongly connected with the changes of mechanical properties after H plasma exposure.…”

Section: Introductionmentioning

confidence: 99%

Irradiation hardening induced by blistering in tungsten due to low-energy high flux hydrogen plasma exposure

Chen

Xiao

Pang

et al. 2019

Journal of Nuclear Materials

View full text Add to dashboard Cite

Where a licence is displayed above, please note the terms and conditions of the licence govern your use of this document. When citing, please reference the published version. Take down policy While the University of Birmingham exercises care and attention in making items available there are rare occasions when an item has been uploaded in error or has been deemed to be commercially or otherwise sensitive.

show abstract

Nanoindentation study of the combined effects of crystallography, heat treatment and exposure to high-flux deuterium plasma in tungsten

Cited by 22 publications

References 34 publications

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Three mechanisms of hydrogen-induced dislocation pinning in tungsten

Recent advances in characterising irradiation damage in tungsten for fusion power

Irradiation hardening induced by blistering in tungsten due to low-energy high flux hydrogen plasma exposure

Contact Info

Product

Resources

About