The characterization of the neutron environment in a reusable facility for irradiation of metallurgical specimens, located at the Ford Nuclear reactor in Michigan, was performed with a combination of transport calculations, extensive dosimeter measurements, and neutron spectrum adjustment. The average difference between the calculated and “measured” reaction rates was ̃7 & (the calculations underpredicted the measurements), and the average absolute difference was ̃10 &. Therefore, the calculations and measurements agreed very well. The flexible facility performed excellently during several years of operation but was discontinued when the Ford reactor ceased operation. The heavy-section steel irradiation (HSSI) program is taking the initial steps toward selecting a site for a new irradiation facility, similar to the one described here.