[en] The plasma facing components (PFCs) of a fusion device such as the first wall (FW), test blanket module (TBM), and divertor, will suffer a high heat load from the plasma and a nuclear heating. Therefore in order to develop the first wall of the ITER (International Thermonuclear Experimental Reactor), it is essential to have the technology and a facility for a heat load test. In order to test a PFC at a high heat flux relevant to the ITER condition, we need a high power beam facility such as JUDITH (Germany), JEBIS (Japan), EBTS (USA), and TSEFEY (Russia). As a part of the ITER project, we need to build such a facility in the near future. As a preliminary work, we constructed a small scale heat load test facility by using a halogen lamp and we performed a heat flux test for the ITER first wall mockup which was made with Cu-alloy and STS316L