Brittle fracture and the brittle-to-ductile transition of tungsten

Gumbsch, Peter

doi:10.1016/j.jnucmat.2003.08.009

Cited by 171 publications

(83 citation statements)

References 49 publications

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“…However, at near-room temperatures the stress relaxation results in plastic deformation and crack formation inside the grains. Thus, the temperature dependence of the structure modification correlates well with the temperature dependence of fracture toughness for W [18,19].…”

mentioning

confidence: 54%

Temperature dependence of surface topography and deuterium retention in tungsten exposed to low-energy, high-flux D plasma

Alimov

Shu

Roth

et al. 2011

Journal of Nuclear Materials

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mentioning

confidence: 54%

Temperature dependence of surface topography and deuterium retention in tungsten exposed to low-energy, high-flux D plasma

Alimov

Shu

Roth

et al. 2011

Journal of Nuclear Materials

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“…As illustrated for the example of recrystallized W [7], at exposure temperatures above the brittle-to-ductile transition temperature (BDTT) (370-470 K depending on the crystal-lattice orientation [ 20 ]) the dislocation mobility is increased and the stress can be relaxed by dislocations moving along lattice planes through the whole crystallite leading to formation of large cavities (100-1000 µm 3 ) at the grain boundaries at depths of several tens of micrometers [7]. This corresponds to the material migration above the surface, i.e., the blister-like surface topography.…”

Section: Discussionmentioning

confidence: 99%

Temperature dependence of surface morphology and deuterium retention in polycrystalline ITER-grade tungsten exposed to low-energy, high-flux D plasma

Alimov¹,

Tyburska-Püschel²,

Lindig³

et al. 2012

Journal of Nuclear Materials

116

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“…Tungsten is known to have certain unfavourable properties hindering its use as a plasma-facing material (PFM), such as susceptibility to surface cracking under ELM-like transient heat loads [5] due to the high brittle-to-ductile transition temperature [6]. Several alloys were proposed with advantages in the sense of thermo-mechanical properties, one of such alloys being W-Ta [7].…”

Section: Introductionmentioning

confidence: 99%

Depth profiling of the modification induced by high-flux deuterium plasma in tungsten and tungsten–tantalum alloys

et al. 2014

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The present work reports the results of an experimental study of the depth distribution and fluence dependence of deuterium plasma-induced material modification of tungsten and tungsten-tantalum alloys. Plasma-induced damage was created by exposure to high-flux deuterium plasma in the plasma generator Pilot-PSI, followed by the degassing and subsequent decoration of created defects with deuterium by another plasma exposure. The depth distribution of deuterium from the decorating exposure reflects the distribution of plasma-induced defects. Depth profiling of this decorating deuterium, was performed by nuclear reaction analysis. It was found that plasma-induced material modification, which manifested itself as an increase of the deuterium concentration in the samples pre-exposed with high-flux plasma in comparison to the samples without such pre-exposure extends down to more than 5 µm from the surface. This increase features a tendency to saturation with increasing fluence of the damaging high-flux plasma. Over the entire probing range, with the exception of the narrow surface region and the deep region beyond 5 µm, the deuterium content is lower in pre-exposed W-Ta than in similarly pre-exposed W. Sub-surface features formed as a result of high-flux plasma exposure were studied with the help of focused ion beam cross-sectioning. W was found to contain plasma-induced cavities down to much larger depth than W-Ta.

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Brittle fracture and the brittle-to-ductile transition of tungsten

Cited by 171 publications

References 49 publications

Temperature dependence of surface topography and deuterium retention in tungsten exposed to low-energy, high-flux D plasma

Temperature dependence of surface topography and deuterium retention in tungsten exposed to low-energy, high-flux D plasma

Temperature dependence of surface morphology and deuterium retention in polycrystalline ITER-grade tungsten exposed to low-energy, high-flux D plasma

Depth profiling of the modification induced by high-flux deuterium plasma in tungsten and tungsten–tantalum alloys

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