Nuclear reactor operation and safety are connected with a nuclear fuel design and its material and geometry properties. An increase in nuclear safety is therefore based on a neutronic and thermal analysis of the materials used in a core. This paper analyzes neutronic properties of a VVER-1200 fuel assembly with alternate fuel and cladding materials that consider Accident Tolerant or Advanced Technology Fuels (ATF). The ATF nuclear fuel development started with the post-Fukushima efforts and its main purpose is a reduction of the high-temperature hydrogen production from the zirconium water reaction. Five ATF cladding candidates with reference Zr-based alloy are studied in this paper as well as six ATF fuel candidates together with an additional standard UO2 reference case. The results are analysed based on the multiplication characteristics, reactivity feedbacks, and spent nuclear fuel composition.