Low Aspect Ratio (LAR) Tokamak

as an excellent neutron source

was effectively applied in early stage of the fusion energy study. This paper offers a novel Liquid Metal (LM) blanketing Cu Center Conductor Post (CCP) design

instead of conventional CCP

for LAR Tokamak. It mainly comprises two parts: a shielding zone which can breed tritium with LM Pb83Li17 and protect Cu center conductor from radiation damage; and an electrical conducting zone which can load high electrical current (>10MA). By comparing it with the conventional CCP

its own merits are shown as follows: reducing radiation damage in the shielding zone

enhancing neutron utilization ratio and tritium breeding ratio

and retaining relative low electrical ohmic power loss with optimized structure of Cu conductor.