The Advanced Reactor Technologies (art) Graphite R&D Program

•The DOE Advanced Reactor Technologies (ART) Graphite R&D program was initiated in 2005 to provide unirradiated and irradiated material data of new nuclear graphite grades.•Three primary areas of research (irradiation testing, unirradiated testing, and material science analysis) combine to provide a comprehensive understanding of the available commercial graphite grades.•The Advanced Graphite Creep (AGC) Experiment will irradiate over 2000 graphite specimens to dose levels of 15 dpa and over irradiation temperatures of 600 °C and 800 °C.•The unirradiated as-manufactured material properties test program (Baseline program) utilizes full-sized ASTM test specimens, a large sample population, and established test standards.•Material analysis program focuses on analyzing the data from the AGC and Baseline programs, effects of degradation (oxidation, fracture, and irradiation damage), and the development of predictive behavior models.