Analysis of the advanced PWR cell MOX fuel using SiC, Zr, FeCrAl, and SS-310 as cladding materials

In this paper, the WIMSD-5B code is used to simulate SiC (Silicon carbide), FeCrAl (ferritic), SS-310 (stainless steel 310), and Zirconium as cladding materials in an advanced PWR (Pressurized Water Reactor) pin cell. Reactivity, cycle length, radial power distribution of fuel pellets, reactivity coefficients, spectrum hardening, and thermal neutron fluxes are all studied for the prospective cladding materials. The neutron economy given by the Zr and SiC models is investigated using unit cell burnup estimates. From the standpoint of achieving the same discharge burnup as the Zircaloy cladding, the study also gave the geometric conditions of all cladding materials under consideration in terms of the relationship between fuel enrichment and cladding materials. In comparison to Zr, the SiC model was found to help extend the life cycle by 2.23 percent. In comparison to Zircaloy, materials other than SiC significantly reduced discharge burnup. Furthermore, in the pellet perimeter, the claddings with lower capture cross-sections (SiC and Zr) have higher relative fission power. The simulation also revealed that by employing SiC and 4.3% MOX fuel, the EOC irradiation value of Zr may be satisfied. The higher absorbing materials (SS-310 and FeCrAl) have more negative FTCs and MTCs at the BOC when it comes to the reactivity coefficient.