Brittle fracture initiation in decommissioned boiling water reactor pressure vessel head weldShow others and affiliations
2022 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 569, article id 153925Article in journal (Refereed) Published
Abstract [en]
The brittle fracture initiation behavior and fracture toughness in the ductile-to-brittle transition region for a thermally-aged weld metal of a decommissioned reactor pressure vessel head (in operation at 288 degrees C for 23 effective full power years) and in the non-aged reference condition were investigated. The results show that brittle fracture initiated primarily from non-metallic inclusions. The correlation between frac-ture toughness and brittle fracture initiation type (inclusion debonding or breakage), initiator size, initi-ation location (as-welded or re-heated regions in the weld metal) were analysed. Despite that thermal ageing does not affect significantly the fracture toughness, it could promote the debonding as a brit-tle fracture primary initiation type. The influence of debonded inclusion on the evolution of cumulative damage and brittle fracture initiation was assessed using crystal plasticity modelling.
Place, publisher, year, edition, pages
Elsevier BV , 2022. Vol. 569, article id 153925
Keywords [en]
Brittle fracture, Initiation, Reactor pressure vessel, Weld metal, Inclusion, Toughness
National Category
Metallurgy and Metallic Materials
Identifiers
URN: urn:nbn:se:kth:diva-316309DOI: 10.1016/j.jnucmat.2022.153925ISI: 000834617900005Scopus ID: 2-s2.0-85134802664OAI: oai:DiVA.org:kth-316309DiVA, id: diva2:1686836
Note
QC 20220811
2022-08-112022-08-112022-08-11Bibliographically approved