A large amount of radioactive concrete waste was generated during the decommissioning work of the Korean Research Reactor #2 (KRR-2). More than 85% of the dismantled concrete waste will be disposed of by a recycling or landfill by the application of a clearance principle. Currently, the Korean Atomic Energy Act and relevant regulation comply with the international recommendation of the sources/practices meeting an individual dose criterion 10 Sv/y and a collective dose criterion of less than 1 man.Sv/y. A variety of radionuclides was generated in the biological shield concrete by a neutron reaction during the operation of a reactor. The specific activities of these radionuclides were measured by using the developed methods and procedures. For the evaluation of a radiological dose, seven scenarios were selected which encompassed a realistic situation of a recycling such as a road construction and landfill disposal route. The external and internal exposure doses of each scenario were calculated by using the MCNP4C code and a mathematical model respectively. The dose assessment regarding the residents and industrial workers was evaluated by using the RESRAD code for the landfill disposal scenario. The maximum individual dose rate was 7.21Sv/y and the maximum collective dose was 0.05 man Sv/yr for the landfill disposal scenario.