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000904069 1001_ $$0P:(DE-HGF)0$$aRieth, M.$$b0$$eCorresponding author
000904069 245__ $$aFabrication routes for advanced first wall design alternatives
000904069 260__ $$aVienna$$bIAEA$$c2021
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000904069 520__ $$aIn future nuclear fusion reactors, plasma facing components have to sustain specific neutron damage. While the majority of irradiation data provides a relatively clear picture of the displacement damage, the effect of helium transmutation is not yet explored in detail. Nevertheless, available results from simulation experiments indicate that 9%-chromium steels will reach their operating limit as soon as the growing helium bubbles extent a critical size. At that point, the material would most probably fail due to grain boundary embrittlement. In this contribution, we present a strategy for the mitigation of the before-mentioned problem using the following facts. (1) The neutron dose and related transmutation rate decreases quickly inside the first wall of the breeding blankets, that is, only a plasma-near area is extremely loaded. (2) Nanostructured oxide dispersion strengthened (ODS) steels may have an enormous trapping effect on helium, which would suppress the formation of large helium bubbles for a much longer period. (3) Compared to conventional steels, ODS steels also provide improved irradiation tensile ductility and creep strength. Therefore, a design, based on the fabrication of the plasma facing and highly neutron and heat loaded parts of blankets by an ODS steel, while using EUROFER97 for everything else, would extend the operating time and enable a higher heat flux. Consequently, we (i) developed and produced 14%Cr ferritic ODS steel plates and (ii) optimized and demonstrated a scalable industrial production route. (iii) We fabricated a mock-up with five cooling channels and a plated first wall of ODS steel, using the same production processes as for a real component. (iv) Finally, we performed high heat flux tests in the Helium Loop Karlsruhe, applying a few hundred short and a few 2 h long pulses, in which the operating temperature limit for EUROFER97 (i.e. 550 °C) was finally exceeded by 100 K. (v) Thereafter, microstructure and defect analyses did not reveal critical defects or recognizable damage. Only a heat affected zone in the EUROFER/ODS steel interface could be detected. However, a solution to prohibit the formation of such heat affected zones is given. These research contributions demonstrate that the use of ODS steel is not only feasible and affordable but could make a decisive difference in the future design and performance of breeding blankets
000904069 536__ $$0G:(DE-HGF)POF4-134$$a134 - Plasma-Wand-Wechselwirkung (POF4-134)$$cPOF4-134$$fPOF IV$$x0
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000904069 7001_ $$0P:(DE-HGF)0$$aDürrschnabel, M.$$b1
000904069 7001_ $$0P:(DE-HGF)0$$aBonk, S.$$b2
000904069 7001_ $$0P:(DE-HGF)0$$aAntusch, S.$$b3
000904069 7001_ $$0P:(DE-Juel1)129778$$aPintsuk, G.$$b4
000904069 7001_ $$0P:(DE-HGF)0$$aAiello, G.$$b5
000904069 7001_ $$0P:(DE-HGF)0$$aHenry, J.$$b6
000904069 7001_ $$0P:(DE-HGF)0$$ade Carlan, Y.$$b7
000904069 7001_ $$00000-0002-7863-6290$$aGhidersa, B.-E.$$b8
000904069 7001_ $$0P:(DE-HGF)0$$aNeuberger, H.$$b9
000904069 7001_ $$0P:(DE-HGF)0$$aRey, J.$$b10
000904069 7001_ $$0P:(DE-HGF)0$$aZeile, C.$$b11
000904069 7001_ $$0P:(DE-HGF)0$$aDe Wispelaere, N.$$b12
000904069 7001_ $$00000-0002-8094-281X$$aSimondon, E.$$b13
000904069 7001_ $$0P:(DE-Juel1)141929$$aHoffmann, J.$$b14
000904069 773__ $$0PERI:(DE-600)2037980-8$$a10.1088/1741-4326/ac2523$$gVol. 61, no. 11, p. 116067 -$$n11$$p116067 -$$tNuclear fusion$$v61$$x0029-5515$$y2021
000904069 8564_ $$uhttps://juser.fz-juelich.de/record/904069/files/Rieth_2021_Nucl._Fusion_61_116067.pdf$$yOpenAccess
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