Neutronic analysis of the HCPB TBM in ITER utilizing an advanced integral approach

Abstract Nuclear design analyses were performed for the new vertical design of the HCPB (Helium Cooled Pebble Bed) Test Blanket Module (TBM) in ITER utilizing an advanced integral approach. The related neutronics calculations were performed with the Monte Carlo code MCNP5 using the latest MCNP geometry model of ITER, named “A-lite”. The TBM model was generated with the geometry conversion tool McCad on the basis of a dedicated CAD model and integrated into one half of the equatorial test blanket port of the A-lite model. The neutronic calculations provided assessments of the total tritium and heat production in the TBM and its components as well as evaluations for the detailed spatial distributions of the neutron flux and the power density. Fine mesh tally calculations were utilized to provide high fidelity results for the distributions that enable identification of crucial issues.