Abstract
The high strength (α+β)- and α-titanium alloys are considered as a candidate materials for flexible attachments of the shield blanket modules in the ITER reactor owing to their advantageous combination of properties, i.e. low elasticity modulus, high resistance to impact loading, high strength, low density and low thermal expansion coefficient. There are limited data available on the irradiation behaviour of these materials. Neutron irradiation of (α+β) Ti–6Al–4V alloy has been performed in the framework of the ITER R&D program. Specimens from two heats of Ti–6Al–4V alloys were irradiated in the IVV-2M reactor up to a dose of 0.35–0.42 dpa at temperatures 240–260 °C. This paper describes the tensile, low cycle fatigue and fracture toughness properties of Ti–6Al–4V alloy in the unirradiated condition and after neutron irradiation.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
