Effect of recrystallization on the fracture toughness of tungsten

Babak, A. V.

doi:10.1007/bf00795612

Cited by 19 publications

(3 citation statements)

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“…However, improvement of thermo-mechanical properties of W materials are still required to overcome the potential disadvantages of W materials, and then to provide an additional margin of safety, reliability, and lifetime of PFCs. The most critical issues affecting the thermo-mechanical properties of W materials are ductile-to-brittle transition [3][4][5][6][7][8][9][10][11] and recrystallization [12][13][14][15]. Most of W materials show the ductile-to-brittle transition above room temperature (low temperature brittleness of as-fabricated materials) and show brittleness after recrystallization at elevated temperature (embrittlement caused by recrystallization).…”

Section: Introductionmentioning

confidence: 99%

A review of impact properties of tungsten materials

Nogami

Watanabe

Reiser

et al. 2018

Fusion Engineering and Design

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Section: Introductionmentioning

confidence: 99%

A review of impact properties of tungsten materials

Nogami

Watanabe

Reiser

et al. 2018

Fusion Engineering and Design

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“…Pure tungsten (W) is a primary candidate for the PFMs of divertor of ITER and DEMO because of high melting point, high thermal conductivity, and the other several physical properties. However, low temperature brittleness [2] and embrittlement caused by recrystallization [3] and neutron irradiation [4] are intrinsic issues of W under fusion reactor environment. According to Geach et al [5], it was firstly clarified that the solid solution alloying by rhenium (Re) could improve the ductility of W. The previous studies also reviled that the mechanical properties not only before but after the neutron irradiation were improved due to the alloying by 3%Re [6,7].…”

Section: Introductionmentioning

confidence: 99%

Thermal shock behavior under deuterium plasma exposure of tungsten–tantalum alloys

Nogami¹,

Wirtz²,

Lied³

et al. 2021

Phys. Scr.

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Tungsten-tantalum (W-Ta) alloys for the application to fusion reactor divertor were developed to overcome the issues of W related to the low temperature brittleness, embrittlement by recrystallization, and embrittlement by neutron irradiation. In the present study, the response to cyclic thermal shock tests as well as the fundamental mechanical properties of W-3%Ta and pure W were investigated, which simulated a transient heat load event in the actual divertor environment. Because it was concerned that the effect of deuterium (D) plasma exposure might be much more pronounced in the Ta-alloyed materials, the thermal shock tests were performed under the background steady state D-plasma exposure. Based on the present study, W-3%Ta might be a competitive alloy system from the viewpoint of thermo-mechanical response in the actual divertor environment as well as the fundamental mechanical properties and resistance to recrystallization. RECEIVED

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“…Tungsten (W) is a promising plasma-facing material for fusion reactor divertors because of its high melting point, high thermal conductivity, low tritium retention, and low sputtering rate [1]. However, there remain some drawbacks related to the mechanical properties of W materials, e.g., low temperature brittleness, high ductile-to-brittle transition temperature (DBTT) [2][3][4][5][6][7][8][9][10], recrystallization-induced embrittlement [11][12][13][14], and neutron-irradiation-induced embrittlement [15][16][17][18]. These issues will restrict the operating temperature window of fusion reactor divertors using W as a plasma-facing material.…”

Section: Introductionmentioning

confidence: 99%