Preliminary performance analysis and optimization based on 1D neutronics model for Indian DEMO HCCB blanket

India under its breeding blanket R&D program for DEMO is focusing on the development of two tritium breeding blanket concepts viz. Lead-Lithium cooled Ceramic Breeder (LLCB) and Helium Cooled Ceramic Breeder (HCCB). The study presented in this paper focuses on the neutronic design analysis and optimization from tritium breeding perspective of HCCB blanket. Indian concept has an edge on configuration and is one of the variants of helium cooled solid breeder blanket concepts proposed by several partner countries in ITER. Indian HCCB blanket having Lithium titanate (Li2TiO3) as tritium breeder and Beryllium (Be) as neutron multiplier with RAFMS structure aims at utilizing the low energy neutrons at the rear part of the blanket. The aim of the optimization study is to minimize the radial blanket thickness while ensuring tritium self-sufficiency and provide data for further neutronic design and thermal-hydraulic layout of HCCB blanket. It is found that the inboard and outboard blanket thicknesses of 40 cm and 60 cm respectively can give Tritium Breeding Ratio (TBR) > 1.3, with 60% 6Li enrichment which is assumed to be sufficient to cover potential tritium losses and associated uncertainties. The results also demonstrated that Be packing fraction (PF) has a more profound impact on the TBR as compared 6Li enrichment and the PF of Li2TiO3.