Comprehensive analysis of nuclear clad materials: Neutronics, radiation shielding, and modal assessment

This study comprehensively evaluated five widely used clad materials in nuclear reactors: Zircaloy, FeCrAl (Iron-chromium-aluminium), TiC (titanium carbide), ZrC (zirconium carbide), and SiC (silicon carbide). Neutronic analyses conducted using OpenMC revealed that ZrC achieved the highest keff value of 1.34 with uranium-based fuel, indicating superior neutron economy. Zircaloy performed effectively with thorium-based fuel, achieving a keff value of 1.32. Radiation shielding analyses using Phy-X software showed that ZrC exhibited the lowest Half-Value Layer and Tenth-Value Layer values at 15 MeV, measuring 2.94 cm, indicating its superior radiation absorption capability with a thinner layer. Conversely, SiC required the thickest layer for effective shielding due to its highest HVL and TVL values. Modal analysis confirmed the mechanical suitability of all examined clad materials, with frequency values falling within acceptable limits, ensuring structural integrity and vibration resistance without compromising reactor safety. In conclusion ZrC emerged as the optimal clad material due to its superior neutronic performance with uranium-based fuel, exceptional radiation shielding capabilities, and mechanical reliability. Zircaloy also proved effective for thorium-based applications, highlighting the importance of selecting clad materials that enhance both reactor performance and safety. © 2024 Elsevier B.V.