Investigation of alternative configurations of the LLCB TBM to increase neutronic and thermo-hydraulics performances

Lead lithium ceramic breeder (LLCB) test blanket module (TBM) was proposed by Indian TBM team for ITER tests. It uses lead lithium eutectic alloy for tritium production and cooling, and ceramic breeder to enhance the tritium production rate (TPR). The TBM first wall and outer structural elements are cooled with helium. inary analysis of RF DEMO-S blanket shows some advantage of Indian concept modification. Alternative variants of TBM, corresponding to the proposed modification, are investigated in this paper from thermo-hydraulics and TPR point of view.