CORA (COmputational Methods for Reactor Analysis) centers on developing methods and computational codes for analyzing neutron behavior within nuclear reactor cores, supporting both reactor design and performance evaluation. This includes simulating neutron transport and interactions, optimizing core configurations (fuel assembly arrangement, control rod placement, etc.), and assessing key performance parameters like reactivity, power distribution, temperature profiles, transient behavior, and safety metrics. We focus specifically on code development, verification, and validation using experimental data and benchmarks. Our research also explores advanced numerical methods and models to improve the accuracy and efficiency of reactor simulations, covering both steady-state and transient analyses and potentially incorporating coupled multi-physics simulations.