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Embrittlement of WCLL blanket and its fracture mechanical assessment

Aktaa, Jarir 1; Gaganidze, Ermile 1; Bongioví, Gaetano; Arena, Pietro; Spagnuolo, Gandolfo Alessandro 2; Aiello, Giacomo; Chiovaro, Pierluigi; Bachmann, Christian
1 Institut für Angewandte Materialien – Werkstoff- und Grenzflächenmechanik (IAM-MMI), Karlsruher Institut für Technologie (KIT)
2 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract:

In the European fusion programme, the Water Cooled Lithium Lead breeding blanket (WCLL BB) uses EUROFER as a structural material cooled with water at temperatures between 295 °C–328 °C and a pressure of 155 bar. The WCLL BB will be significantly irradiated (>2 dpa), while some parts will not receive significant heat loads, e.g. the sidewalls or the back-supporting structures. The irradiation, together with the irradiation temperature of EUROFER below 350 °C, produces a shift of the ductile-to-brittle-transition temperature (DBTT) to levels above room temperature at neutron doses, causing material damage as low as 2–3 dpa. Even though the DBTT does not reach the operating temperature level, brittle/non-ductile fracture is a concern during in-vessel maintenance when the BB temperature is below the DBTT. Two loading scenarios were identified as severe in this respect: (i) re-pressurization of the WCLL BB cooling loop after in-vessel maintenance, and (ii) dead weight loads during lifting of the BB segment. The embrittlement of the WCLL BB was investigated by quantifying the local DBTT shift in its parts based on current knowledge of the embrittlement behaviour of EUROFER under neutron irradiation. ... mehr


Verlagsausgabe §
DOI: 10.5445/IR/1000161666
Veröffentlicht am 24.08.2023
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Institut für Angewandte Materialien – Werkstoff- und Grenzflächenmechanik (IAM-MMI)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 09.2023
Sprache Englisch
Identifikator ISSN: 0029-5515, 1741-4326
KITopen-ID: 1000161666
HGF-Programm 31.13.04 (POF IV, LK 01) In Vessel Components
Erschienen in Nuclear Fusion
Verlag International Atomic Energy Agency (IAEA)
Band 63
Heft 9
Seiten Art.-Nr.: 096016
Vorab online veröffentlicht am 04.08.2023
Schlagwörter neutron irradiation, embrittlement, WCLL, breeding blanket, brittle/non-ductile fracture, fracture mechanical assessment
Nachgewiesen in Dimensions
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