Oxide dispersion strengthened (ODS) steels with high Cr-content are extensively investigated in Europe, Japan and United States by the nuclear materials community for application to both advanced ﬁssion reactors and fusion systems. In comparison to standard high Cr-steels, the expected operation temperature range can be extended to 650 C or more because of their improved creep resistance. However, their crack resistance behavior in the high temperature range was less investigated. The aim of the present paper is to provide some insight on their fracture behavior at high temperature and different crack conﬁgurations, in particular shallow crack. Crack resistance measurements were performed on a 12%Cr-ODS steel using compact tension specimens at 650 C considering both shallow and deep crack conﬁgurations. Finite element calculations were performed on a typical fuel cladding tube geometry to assess the performances in terms of crack resistance. It is found that the temperature gradient across the wall should be maintained low enough to avoid cracking. After irradiation in corrosive environment, the boundary conditions might be further affected limiting therefore the lifetime of ODS cladding.