Cracking failure study of ITER-reference tungsten grade under single pulse thermal shock loads at elevated temperatures

Hirai, T.; Pintsuk, G.; Linke, J.; Batilliot, M.

doi:10.1016/j.jnucmat.2009.01.313

Cited by 188 publications

(92 citation statements)

References 5 publications

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“…1). The grain orientation in coupons was perpendicular to the major surfaces, which corresponds to current ITER specifications for the use of tungsten as material in PFCs [8,24].…”

Section: Methodsmentioning

confidence: 64%

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

2012

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Abstract:The oxidation behavior of International Thermonuclear Experimental Reactor (ITER) reference tungsten grade has been evaluated in dry air in the temperature range 600 800 °C. At 600 °C, the scale remained protective while the integrity of W 18 O 49 layer was kept. Rapid increase in mass gain resulted from mas sive cracking at local areas in the W 18 O 49 layer. Then, a coarse non protective columnar WO 2.92 scale was developed which favoured rapid inward oxygen transport into the alloy. At 700 and 800 °C, growth stres ses in the scale were released through local cracking. At this stage, WO 2.92 became progressively trans formed into WO 3 when the oxygen partial pressure increased across the scale thickness.

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“…1). The grain orientation in coupons was perpendicular to the major surfaces, which corresponds to current ITER specifications for the use of tungsten as material in PFCs [8,24].…”

Section: Methodsmentioning

confidence: 64%

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

2012

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“…The use of tungsten and tungsten alloys for the helium-cooled divertor and possibly for the protection of the helium-cooled first wall in reactor designs going beyond ITER has been discussed and investigated for several years (see, for example, [1][2][3][4][5][6][7][8]). The structure of the Tungsten and Tungsten Alloys (W&WALLOYS) programme of the EFDA Topical Group on Fusion Materials can be found in [9], which also gives a comprehensive review of activities.…”

Section: Introductionmentioning

confidence: 99%

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Rieth

Dudarev

Vicente³

et al. 2013

Journal of Nuclear Materials

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653

281

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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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Cracking failure study of ITER-reference tungsten grade under single pulse thermal shock loads at elevated temperatures

Cited by 188 publications

References 5 publications

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

On the oxidation mechanism of pure tungsten in the temperature range 600–800°C

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

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

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