The RB-2 research reactor was operated for 17 yr at power levels of the order of 10 kW (1963–1969) and 100 W (1971–1980). During dismantling, the radiological risk for personnel was recognizably low, but radioactivity levels associated with the waste materials and the site itself needed to be evaluated. Predismantling activities consisted of a preliminary radiological characterization, including direct measurements, spectrometric analyses of samples, and theoretical calculations. Determination of “nonradioactive” limits determined the disposition of the site and the transportation routes for the waste materials. After dismantling, the site was extensively monitored for remaining radioactivity. In general, unrestricted release has been achievable for the site; only a small area is still subject to radiological control.