This report documents analysis of irradiated property data from the Advanced Graphite Creep (AGC)-2 graphite specimens. The AGC-2 is the second of a series of six irradiation test trains planned as part of the AGC experiment to fully characterize neutron irradiation, temperature, and radiation creep behavior of various current nuclear graphite grades. The AGC-2 capsule was irradiated in the Idaho National Laboratory Advanced Test Reactor at a nominal temperature of 600°C, beginning with irradiation Cycle 149A on April 12, 2011, and ending with Cycle 151B on May 5, 2012, with a total received dose range of 1.3 to 4.7 dpa. AGC-2 was designed to provide irradiation conditions similar to the first capsule, AGC-1 (i.e., the same graphite grades, a nominal irradiation temperature of 600°C, and the same applied mechanical stress levels), but was irradiated for a shorter period of time to provide material property values for the graphite samples at lower dose range than achieved in AGC-1. Material property and dimensional strain measurements were conducted on specimens from 15 nuclear graphite grades using a similar specimen assembly configuration as AGC-1 to provide a more direct comparison between the two capsules. However, AGC-2 contained an increased number of specimens (i.e., 487 total AGC-2 specimens versus 387 total AGC-1 specimens) and replaced specimens of the minor grade 2020 with the newer grade 2114. Modifications to the AGC-2 capsule design were made to help maintain a narrow range of specimen temperatures. Optimally, specimens would be irradiated as close to 600°C as possible. The AGC-2 creep and control specimen temperatures ranged from 541 to 681°C. 1,2 This was markedly better than the AGC-1 specimen temperature range of 468 to 716°C. 22,3,4 Dose range received by the creep and control specimens ranged from 2.0 to 4.7 dpa. Dose range for the piggyback (button) specimens ranged from 1.3 to 4.7 dpa, because some of these specimens were physically located farther away from the peak centerline region. Data covered in this report include specimen resistivity, elastic modulus (both by sonic resonance method and sonic velocity method), shear modulus, coefficient of thermal expansion, and thermal diffusivity. Experimental variables of irradiation dose, temperature, stress, and graphite grade that affect these property changes are presented with the observations.