Construction of a high temperature and pressure helium supplying system for ITER TBM

One of the major objectives of International Thermonuclear Experimental Reactor (ITER) is to develop a tritium breeding module with self-sufficiency for a power producing nuclear fusion reactor. In Korea, Helium Cooled Solid Breeder (HCSB) Test Blanket Modules (TBM) was proposed to be tested in ITER. In the TBM, high pressure (8 MPa) and high temperature (350-500 .deg. C) helium gas is considered as a coolant and therefore a helium supplying system, one of the essential parts of the TBMs, has been developed. In present study, a scale downed helium supplying system has been designed and constructed at Korea Atomic Energy Research Institute (KAERI) to obtain manufacturing and operational experiences on the helium supplying system and to connect with a high heat load test facility (Korea Heat Load Test Facility-2, KoHLT-2) for examination of various kinds of mock-ups for the TBM structure