Loss of coolant accident and loss of flow accident analysis of the ARIES-AT design

Loss of coolant accident (LOCA) and loss of now accident(LOFA) analysis is performed for ARIES-AT, an advanced fusion power plant design (1000 MWe). A RIES-AT employs a high performance, high temperature blanket system. It use s the high temperature SiC/SiC for structural material and LiPb for coolant -breeder, Due to the large difference between the time scale of plasma shut down and the coolant or power loss, it is assumed that the plasma is immedi ately quenched at the onset of the LOCA/LOFA and the chamber components' te mperature begins to rise due to the decay heat generated. A 2-D transient f inite element model is established to examine the thermal behavior of the i n-vessel components to determine the maximum temperature reached, the time, and duration of the peak. The model is axisymmetric in (r-z) around the re actor axis to show the details of temperature distribution in the vertical direction. The vacuum vessel is assumed adiabatic in the inboard side and r adiates to the maintenance port located on the outboard side. The maximum t emperature of steel in the reactor is about (600 degreesC - 700 degreesC) a fter about 4 days from the onset of the accident. The highest temperature i n the reactor is in the divertor region and it reaches approximate to 1050 degreesC after about 2-3 hours. The analysis indicates that the reactor doe s not need any special scheme for decay heat removal.