Activation analysis and waste management for dual functional lithium-lead blanket of the China Fusion Engineering Test Reactor

Abstract

Based on the design requirements of the first stage of the China Fusion Engineering Test Reactor (CFETR), the activation performance calculation and analysis of the components in the dual function lead-lithium blanket were performed using a neutron transport design and safety evaluation software system (SuperMC) with the fusion evaluation database JEFF3.2. A coupled burnup and transportation calculation method was used to calculate the radioactivity, residual decay heat, dose rate, and potential biological hazards of each component in the equatorial surface of the fusion reactor at different times after shutdown. The waste disposal problem of the tritium breeding blanket after the decommissioning of the fusion reactor was analyzed according to the relevant nuclear waste disposal standards in the safety and environment assessment of fusion power strategy. Results of the analysis show that under the condition of normal operation of 200 MW for 10 years, all components of the breeding blanket in the CFETR can satisfy simple recycling standards and meet the requirements of the first stage of CFETR radioactive waste treatment after 50 a of cooling.

Keywords

• fusion blanket
• material activation
• radioactive waste
• fusion reactor
• monte carlo method