A conductor for ITER toroidal field (TF) coils is the cable-in-conduit conductor (CICC) type, which is made of Nb3Sn superconducting strands encased in a stainless steel tubular jacket. A 120-m-long prototype has been designed in accordance with ITER requirements and manufactured prior to production of 26 full-sized CICC lengths that are the contribution of Russia to the ITER TF magnet system. Ten meters of the prototype have been used to produce a sample for testing in the SULTAN facility in order to qualify the strand/cable/jacket combination. A test aimed at qualifying the conductor performance based on T-cs measurements in representative condition regarding the transport current and magnetic field has been carried out. At the same time, the test was used to compare the conductor behavior after different heat treatment cycles. Each of two legs has been reacted in accordance with one of the specified heat treatment cycles for the ITER TF conductor. Test results are presented and discussed. Based on the test results, the eligibility of the conductor for the ITER TF magnet system has been assessed.