The shielding blanket (SB) system is to provide neutron shielding for Chinese fusion engineering test reactor in-vessel components and the external environment. The SB concept design activities have been carried out during the 2009-2011 campaign. Current design on the SB system is concentrated on neutronics analysis, SB modules design, and mechanics analysis using finite-element method. The neutronics analysis is made progress on the neutron shielding performance of shield materials and the SB thickness estimation in radial direction. A new SB module structure with prewater boxes and radial cooling tubes is proposed in the breeding area, which has the benefit to neutron moderating and heat removal issues. The advantage lies in the increasing coolant volume ratio inside the SB module. The heat removal capability of the SB module and the divertor blanket are explored using computational fluid dynamics (CFD) simulations. In addition, the preliminary mechanics analysis is completed on the electronmagnetic force including structure static stress under core plasma disruption. This paper summarizes SB component design activities and the progress at present status.