Tensile and fatigue properties of potassium doped and rhenium containing tungsten rods for fusion reactor applications

Guan, Wenhai; Nogami, Shuhei; Fukuda, Makoto; Hasegawa, Akira

doi:10.1016/j.fusengdes.2015.11.030

Cited by 18 publications

(18 citation statements)

References 13 publications

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“…It was demonstrated that K-doping not only led to improving tensile strength but also hardly changed the elongation, regardless of the test direction and temperature [24,28]. The ductility of W at low temperatures was enhanced via the K-doping, especially in the direction along the radial [28].…”

Section: Mechanical Properties Of Wkmentioning

confidence: 99%

“…To be more specific, these service conditions include high-energy neutron (14.1 MeV) bombardments, highfluence-rate plasma erosions [10 24 H + m −2 s −1 (1-10 eV), 10 22 -10 24 He 2+ m −2 s −1 (< 500 eV)], and intense thermal loads (up to 20 MW m −2 ) [1,[38][39][40][41][42]. Furthermore, transient pulsed heat loadings (up to GW m −2 ) by major disruptions, vertical displacement events, and edge localized modes could also be applied to the divertor surfaces.…”

Section: Pfms and Wkmentioning

confidence: 99%

“…OSRAM GmbH, Schwabmuenchen [35] manufactured K-doped (6 × 10 −3 -7.5 × 10 −3 wt%) W wires by drawing. Allied Material Corp. [24] produced pure W (PW) and WK rods via using similar powder metallurgy and swaging processes.…”

Section: Preparation Of Wkmentioning

confidence: 99%

“…In W rods with large diameters, K-doping could retard the influence of microstructural anisotropy, especially the ductility during tensile tests. Figure 8 shows the tensile properties: UTS and total elongation of K-doped W (KW in figures) and PW versus temperature [24].…”

Section: Mechanical Properties Of Wkmentioning

confidence: 99%

“…However, the brittleness of W and irradiation-induced damages would inevitably bring some uncertainties when W-based materials are utilized in a deuterium-tritium (DT) reactor. Considerable efforts were dedicated to improving W-based materials for present and near-term experiments [5,6,[17][18][19][20][21][22][23][24][25][26]. Generally speaking, ultrafine grains and nano-structures are widely applied to improve the performances of W in extreme PFM conditions.…”

Section: Introductionmentioning

confidence: 99%

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Tungsten–potassium: a promising plasma-facing material

2019

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Tungsten-potassium (potassium-doped tungsten or WK), initially known from the electric filament industry, is a promising plasma-facing material (PFM) in future fusion facilities like International Thermonuclear Experimental Reactor (ITER). However, the brittle nature of W and irradiation-induced defects of WK materials may result in a risk of deuterium-tritium reaction failure in fusion reactors. Previous studies revealed that advanced W with ultrafine grains and nanostructures might be able to address these problems. However, K-doped W, a rapidly developed material for PFMs, lacks a systematical summary. In this review, we firstly describe the powder metallurgy and plastic deformation for the preparation of WK. Then, the mechanical properties of WK and thermal shock resistance results are reviewed. Important issues such as irradiation damages from neutron, heavy ion, and plasma (H isotope or He) irradiation are also discussed. Hitherto, WK under irradiations shows comparable or even better performances compared with other counterparts such as ITER grade pure tungsten. This review could be benefitial to the future efforts of improving the ductility and irradiation tolerance of WK materials.

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Section: Mechanical Properties Of Wkmentioning

confidence: 99%

Section: Pfms and Wkmentioning

confidence: 99%

Section: Preparation Of Wkmentioning

confidence: 99%

Section: Mechanical Properties Of Wkmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Tungsten–potassium: a promising plasma-facing material

2019

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Neutron irradiation effects on mechanical properties of ITER specification tungsten

et al. 2021

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In this contribution, we present the results of recent neutron irradiation campaign performed in the material test reactor BR2 (Belgium) on pure tungsten. We have applied various irradiation conditions and sample geometry to assess the effect of neutron irradiation on hardness, bending, tensile and fracture mechanical properties. The investigated material is a commercially pure tungsten plate fabricated according to the international thermonuclear experimental reactor (ITER) specification for the application in the divertor plasma-facing components. The neutron irradiation covers a large span of temperatures and damage doses, ranging from 600 to 1200 °C and 0.1-1 dpa. The obtained mechanical properties were analyzed to deduce the shift of the ductile to brittle transition temperature (DBTT) applying bending, tensile and fracture toughness-testing procedures. Then, a correlation of the fracture toughness with the change of the hardness was established. The obtained results are compared with the already published results on another ITER specification grade produced in the form of a rod. The presented and discussed results show that the performance of the compared grades in terms of the irradiation-induced embrittlement is similar, and that the irradiation in the high-temperature region (600-800 °C) causes a considerable DBTT shift already at 0.2-0.5 dpa.

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