The advancement of Accident-Tolerant Fuel (ATF) technologies has led to the introduction of novel cladding materials that exhibit superior oxidation resistance and enhanced thermal and mechanical properties compared to conventional zirconium-based alloys. The options being studied are chromium-coated zirconium-based alloys, silicon carbide, and iron-based alloys. These innovative materials are designed to improve safety margins and minimize hydrogen production during severe accident scenarios. Their unique thermal and neutronic properties may significantly influence core neutronic parameters. This study offers a comparative evaluation of the impact of ATF cladding on CR worth and reactivity coefficients, employing 3D whole core simulations for an APR-1400. The reactivity coefficients studied are the isothermal temperature coefficient, moderator temperature coefficient, Doppler coefficient, boron coefficient, and power coefficient. The CASMO-4E/SIMULATE3 code system is utilized to carry out the calculations needed. This study reveals the safety and performance effects of integrating ATF cladding materials into nuclear reactors. Gaining a comprehensive understanding of these effects is crucial for optimizing control strategies and bolstering the accident tolerance of contemporary nuclear systems.