Evaluation of radioactive waste generated from the Compact Reversed Shear Tokamak reactor (CREST)

Radioactive waste generated from the CREST reactor has been evaluated. Acti vation of blankets and shields used during a plant lifetime was evaluated b y an activation calculation code taking into accounts of the distribution o f neutron wall loading and the scenario of blanket replacement. Limits on s urface dose limits define the feasibility of recycling by remote handling ( RHR) and by hands-on operation (HOR). After 50 years for decay of activated components, surface dose rate of most of components exceeds 10 mSv/h and c annot be recycled. Some of shields are lower than 10 mSv/h and have a possi bility of RHR. After 100 years, surface dose rate of all components is lowe r than 3 mSv/h, and RHR is feasible. Half of shields are lower than 0.01 mS v/h and have a possibility of HOR. After 225 years, dose rate of all compon ents is lower than I mSv/h. RHR with a relatively simple shielding precauti on may be feasible In the cases of 150 years or later, little degradation o f dose rate can be expected. Therefore, the used components should be manag ed within approximately 125 years by suitable methods.