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Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technology

Rieth, M.; Dürrschnabel, M.; Bonk, S.; Pintsuk, G.; Aiello, G.; Henry, J.; Carlan, Y. de; Ghidersa, B.-E.; Neuberger, H.; Rey, J.; Zeile, C.; De Wispelaere, N.; Simondon, E.; Hoffmann, J.

A major part in the EUROfusion materials research program is dedicated to characterize and quantify nuclear fusion specific neutron damage in structural materials. While the majority of irradiation data gives a relatively clear view on the displacement damage, the effect of transmutation – i.e. especially hydrogen and helium production in steels – is not yet explored very well. However, few available results indicate that EUROFER-type steels will reach their operating limit as soon as the formation of helium bubbles reaches a critical amount or size. At that point, the material would fail due to embrittlement at the considered load.

This paper presents a strategy for the mitigation of the before-mentioned problem using the following facts:

• the neutron dose and related transmutation rate decreases quickly inside the first wall, that is, only a plasma-near area is extremely loaded

• nanostructured oxide dispersion strengthened (ODS) steels may have an enormous trapping effect on helium and hydrogen, which would suppress the formation of large helium bubbles

• compared to conventional steels, ODS steels show improved irradiation tensile ductility and creep strength
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Verlagsausgabe §
DOI: 10.5445/IR/1000130268
Veröffentlicht am 05.03.2021
DOI: 10.1016/j.fusengdes.2021.112275
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsjahr 2021
Sprache Englisch
Identifikator ISSN: 0920-3796, 1873-7196
KITopen-ID: 1000130268
HGF-Programm 31.13.04 (POF IV, LK 01) In Vessel Components
Erschienen in Fusion Engineering and Design
Verlag Elsevier
Band 166
Seiten Art.-Nr.: 112275
Schlagwörter Blanket first wall; Mockup; High heat flux test; Helium cooling loop; Materials technology; Engineering
Nachgewiesen in Scopus
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