The Demonstration Poloidal Coil (DPC) program for investigation of large superconducting pulse-coil technology required for Fusion Experimental Reactor (FER) has been conducted. In this program, there are three superconducting pulse coils (DPC-U1, U2, and EX) so as to simulate mechanical interaction of real pulse coils in fusion reactor. These coils are forced-flow pulse coils with a cable-in-conduit conductor and are designed to be cooled by supercritical helium at 350 g/sec under conditions of 10 bar and below 4 K. For this purpose, a new cryogenic pump system, which is composed of a circulation pump and a cold compressor, is developed. In addition, a newly developed current lead with a cable-inconduit shape has been selected for the current leads and its rated current and insulation testing voltage are specified to be 30 kA and AC 16 kV, respectively. The latest design status of the whole cryogenic system and the verification test results of the cryogenic devices such as the cryogenic pump system and current lead are described in this paper.