Abstract
The relevance of work is determined by the fact that development of irradiated beryllium recycling method in nuclear industry is environmentally and economically proven step. Currently the feasibility study to develop such method is carried out in the IAE RSE NNC RK. Determination of beryllium activity spent in nuclear power facilities will allow to evaluate and define conditions for studying of irradiated beryllium. Activity calculations of beryllium activation samples and impurities irradiated in JMTR reactor for several years have been carried out. The dose rate of gamma irradiation from irradiated beryllium sample at work places close to a plant, operation time at these places and permissible doses to the personnel were determined. Calculation results will be used at preparation for reprocessing of irradiated beryllium and for future RW management resulted from purification. During operation of the plant for purifying irradiated beryllium, liquid and solid RW will be generated. The paper provides the methods of RW management.