Abstract: In order to meet the requirement of ITER toroidal field ripple effect, a new design of helium-cooled solid breeder test blanket module (HCSB-TBM) with reduced low activation ferritic martensitic stainless steel (LAFM) was proposed by Southwestern Institute of Physics. By using MCNP code and global ITER MCNP model, 3D neutronics calculations for the new 2×6 HCSB-TBM design were performed and the results of tritium generation rate, nuclear heating deposit and power density distribution were obtained. The tritium production rate is about 12.68 mg/d while considering ITER duty factor of 22%. The TBM total nuclear heating deposit is about 522.5 kW, and the peak power density is 11.8 W/cm³ which appears in Li₄SiO₄. The results can provide neutronics data for TBM further structural and thermal-hydraulic optimization and design of other systems.