Evaluation of radioactive waste generated from the compact reversed shear tokamak reactor (CREST)

摘要

Radioactive waste generated from the CREST reactor has been evaluated. Activation of blankets and shields used during a plant lifetime was evaluated by an activation calculation code taking into accunts of the distribution of neutron wall loading and the scenario of blanket replacement. Limits on surface 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 cannot be recycled. Some of shields are lower than 10 mSv/h and have a possibility of RHR. After 100 years, surface dose rate of all componejts is lower than 3 mSv/h, and RHR is feasible. Half of shields are lower than 0.01 mSv/h and have a possibility of HOR. After 125 years, dose rate of all components is lower than 1 mSv/h. RHR with a relatively simple shielding precaution may be feasible. In the cases of 150 years or later, little degradation of dose rate can be expected. Therefore, the used components should be managed within approximately 125 years by suitable methods.