Neutronics performance parameters for the US dual coolant lead lithium ITER test blanket module

Abstract

Neutronics analysis was performed for the reference design of the US dual coolant lead lithium (DCLL) ITER test blanket module (TBM). Detailed CAD models were utilized in the analysis. Relevant nuclear performance parameters were determined. These include tritium breeding, nuclear heating, radiation damage, transmutations, and shielding requirements. The calculated tritium breeding ratio (TBR) in the DCLL TBM is 0.561 and the total nuclear heating is 0.574 MW. For the ITER fluence goal of 0.3 MWa/m <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">2</sup> , the peak cumulative radiation damage and He production in the first wall (FW) are 5.1 dpa and 56 appm, respectively. Mg builds up in the SiC flow channel inserts (FCI) to ~100 appm with possible impact on electrical and thermal conductivities. About 1.2 m thick shield is required behind the TBM to allow personnel access for maintenance.