Abstract
In this paper, neutronic calculations were performed to obtain tritium breeding ratio (TBR) for ITER device using developed helium cooled pebble (HCPB) blanket. The designed blanket module has the following combinations; natural lithium, Li4SiO4 (20 %), beryllium moderator and neutron multiplier. To ensure tritium self-sufficiency, the calculated achievable TBR should be equal to or greater than the required TBR. Simulations have been performed by means of Monte Carlo MCNP-4C code using END/B-VII.1 data library. Results show that TBR of 1.14 is obtained for this new HCPB.
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