Eurofer Steel, Development to Full Code Qualification

Abstract

European Union fusion materials community has been developing a reduced activation martensitic steel called Eurofer for almost 2 decades. This steel has now reached maturity and is being proposed for addition to RCC-MRx. At first, its code qualification is sought for ITER Test Blanket Modules, where the maximum irradiation dose is low, <3 dpa, reactor pulses are of short durations, <500 s, and nominal service temperature does not exceed 550 °C. The ultimate goal, however, is to extend its qualification to DEMO and fusion power reactors, where irradiation doses >70 dpa and continuous operation are anticipated. In this paper, after a brief recall of the Eurofer steel development, types of materials and joints used during its characterization are presented. This is followed by the procedures employed for establishment of its materials properties databases and determination of its design allowable values, with emphasis on creep, fatigue and creep-fatigue properties.