A conceptual design was preformed to determine the feasibility of irradiating silicon carbide fiber reinforced /silicon carbide (SiCf/SiC) and carbon fiber reinforced /carbon (Cf/C) tensile test specimens for the Next Generation Nuclear Production (NGNP) program. The design was based on the Flux Trap, Large and Small B irradiation positions in the Advanced Test Reactor. The Test Specimens investigated were 50% SiCf/SiC composites and 50% Cf/C composites. The specimens geometry were either tapered or fillet type dog bone shape, 25 to 35 mm long with a gauge length of 20 mm, width 6 mm, and 3 mm thick. The width of the support end of the specimens was 10-12 mm. The test specimens require finite temperature control from 600 to 1,000 oC. Due to the high temperatures required for the test specimens, the adjacent components will need to be fabricated from composite or graphitic materials. One-third to one-half of the specimens will be unloaded but will have the same geometry and irradiation conditions as the tensile specimens. The desired specimen irradiations damage was 9 dpa and the desired tensile stress limits were from 10 to 30 MPa. One of the design objectives was to load the test train so that single or multiple specimen failures would not compromise the entire test train. This need was realized from previous irradiations where the specimens were all loaded through a single load path. Any specimen failure along the load path resulted in the entire test train to become unloaded. Another design objective was to determine the best irradiation position that would maximize the target space but still provide the neutron flux needed to complete the irradiations in a reasonable amount of time. A rough order of magnitude cost estimate and schedule was completed based on previous experiments. The corresponding risk assessment was performed to identify possible items that may affect the overall project success. Depending upon how the risks are mitigated, the cost and schedules may be impacted.