Activation and safety assessment of the ARIES-ST design

Activation and Safety analyses were performed for the ARIES-ST design. The ARIES-ST power plant includes a water cooled copper center post and uses a SiC/LiPb blanket. The first wall and shield are made of low activation ferr itic steel and cooled with helium. The center post, first wall, inboard shi eld and blanket were assumed to survive for 2.6 full power years (FPY). On the other hand, the outboard shield and vacuum vessel were assumed to stay in place for 40 FPY. Neutron transmutation of copper resulted in the produc tion of several nickel, cobalt and zinc isotopes. The production of these i sotopes resulted an increase of the time-space average resistivity of the c enter post by about 6% after 2.6 FPY. All of the plant components met the l imits for disposal as Class C low level waste (LLW). The off-site doses pro duced at the onset of an accident are caused by the mobilization of the rad ioactive inventory present in the plant. Analysis of a Loss of Coolant Acci dent (LOCA) indicated that the first wall and shield would reach a maximum temperature of less than 700 degrees C during the accident. The calculated temperature profiles and available oxidation-driven volatility experimental data were used to calculate the dose at the site boundary under conservati ve release conditions. The current design produces an effective whole body early dose of 1.77 mSv at the site boundary.