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000875314 1001_ $$0P:(DE-HGF)0$$aNogami, S.$$b0
000875314 245__ $$aThermal shock behavior of potassium doped and rhenium added tungsten alloys
000875314 260__ $$aStockholm$$bThe Royal Swedish Academy of Sciences$$c2020
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000875314 520__ $$aHigh ductile-to-brittle transition temperature, recrystallization-induced embrittlement, and neutron-irradiation-induced embrittlement are potential drawbacks related to the mechanical properties of tungsten (W) for plasma facing materials of fusion reactor divertors. To improve the mechanical properties, resistance to recrystallization and neutron irradiation, W materials modified by potassium doping and alloying by rhenium have been developed. In this paper, thermal shock behaviors of these W materials under high heat flux tests were investigated, which simulated an edge localized mode of plasma occurring in fusion reactors as a transient event. The thermal shock tests were performed with an electron beam facility, JUDITH 1, and post-mortem analyses to evaluate the damage caused by the thermal shock tests were carried out.
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000875314 7001_ $$0P:(DE-Juel1)129778$$aPintsuk, G.$$b1$$ufzj
000875314 7001_ $$0P:(DE-HGF)0$$aMatsui, K.$$b2
000875314 7001_ $$0P:(DE-HGF)0$$aWatanabe, S.$$b3
000875314 7001_ $$0P:(DE-Juel1)129811$$aWirtz, M.$$b4
000875314 7001_ $$0P:(DE-Juel1)129751$$aLoewenhoff, T.$$b5$$eCorresponding author
000875314 7001_ $$0P:(DE-HGF)0$$aHasegawa, A.$$b6
000875314 773__ $$0PERI:(DE-600)1477351-x$$a10.1088/1402-4896/ab3dcc$$gVol. T171, p. 014020 -$$p014020 -$$tPhysica scripta$$vT171$$x1402-4896$$y2020
000875314 8564_ $$uhttps://juser.fz-juelich.de/record/875314/files/Pintsuk_Postprint.pdf$$yPublished on 2020-02-27. Available in OpenAccess from 2021-02-27.
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