Abstract: Beryllium has obvious advantages according to other kinds of the first-wall protecting materials in fusion power reactors. Be, W and carbon-based materials were considered the candidates of structural materials for the first-wall of International Thermal Experimental Reactor (ITER). When we neglect the neutron load, the analysis results of multiphysics simulation on the first-wall of Chinese helium-cooled solid breeder test blanket module (CH HCSB TBM) show that the simulative result is clearly different with other results in the paper. So we believe that we have to calculate the neutron load when proceeding the simulating thermal load analysis on surface of the TBM. The results of thermal structural analysis on the first-wall clarify that the stress on Be is exceeded the allowable stress of the material. Beryllium alloys or other first-wall protecting materials should be found to satisfy the requirements of thermal structural stress.