We design a volumetric neutron source for testing large-scale blanket components, based on a steady-state tokamak device with super-conducting coils. It is found that the neutron flux of 1 MW/m² is available in the medium-sized device (R = 4.5m, a = 1.0 m, k = 1.8 and I_p = 5.6 MA) under the conditions of H = 2 and b_N = 3 with a NBI power of 60 MW. We demonstrate the controllability of the current profiles required for high beta plasma up to b_N = 3 with the combination of the bootstrap current and NB-driven current (E_b = 1.0 MeV). Since the tritium consumption is about 10 kg a year, we have to install a breeding blanket. Here we design water-cooled and austenitic stainless steel-structured breeding blanket system, and employ the Li-Pb breeder. Compared with ceramic breeding materials, in general, the Li17Pb83 breeder has a potentiality for high tritium breeding ratio. The compatibility of Li-Pb with stainless steel is acceptable at low temperature and at low flow velocity, and water coolant can be introduced. The calculated local TBR reaches 1.4 or more in Li-Pb breeder at a sufficient thickness of breeding zone. The net TBR might reach the acceptable value only with the outboard Li-Pb blanket, since the tritium breeding contribution of the outboard blanket is relatively higher than its coverage. The temperature distribution in the breeding region of Li-Pb blanket can be controlled to avoid corrosion of the structure material with double-walled cooling panel. Since the inboard thickness play an important role for plasma performance, we optimize the shielding material by introducing tungsten in addition to the mixture of stainless steel and boric water. The calculation results show that a 40% volume fraction of tungsten in the shield region provides the minimum nuclear response in the TFC, making the reduction by about 30 cm in the inner region.