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Activation and shielding analyses have been performed for a CN helium-cooled test blanket module (TBM) in the equatorial port of the International Thermonuclear Experimental Reactor (ITER). In this paper, we examine the neutron-induced radioactivity, decay heat, and shutdown contact dose rate for the CN TBM recent design. In addition, we assess the shielding efficiency of TBM to satisfy the nuclear shield requirement of ITER. The A-lite 40 ° ITER 3-D calculation model was used for the neutron transport calculations. Activation analysis was performed using the FISPACT-2007 code with activation cross-section data file EAF-2007. The shutdown dose rate distribution in the zone behind shielding was calculated using the rigorous two-step method. SA2 safety scenario was used as the irradiation scenario for activation analyses. The calculated results were discussed with a target of 100 μSv/h after 12 days of cooling for human access to the zones around the port cell. It was shown that the shield efficiency of the TBM system needs to be improved.