Abstract
The paper addresses issues of providing the representative experiments with fuel rods of fast reactors in central experimental channel of the IGR thermal pulse reactor. Preliminary calculations demonstrated a possibility to receive quite intensive field of fast neutrons in the IGR using converters of various designs. For a shift to such tests of fuel rods of fast reactors in the IGR, experimental substantiation of calculation studies is required. It was suggested to implement the experimental substantiation using a set with two types of fuel rods, one of which operates in thermal spectrum of neutrons and another one – in a neutron spectrum obtained using the converter. The design of such an experimental device has been developed; its performance has been calculated. The safety justification for its testing in the IGR has been carried out.