GENERATION OF NODAL CORE SIMULATOR UTILIZING VERA

Nuclear core simulators based upon few-group nodal diffusion method currently are widely used to predict light water reactor behavior. Nodal parameters’ input, e.g. cross-sections, discontinuity factors, and pin form typically generated utilizing lattice physics codes. In doing so, a number of approximations introduced related using zero current boundary conditions, 2-D radial geometry, uniform thermal conditions in coolant fuel. Usage full models with prediction fidelity typical parameters would eliminate these approximations. The VERA code can serve as such model was so utilized this work. Via subsequent processing predictions, for range state points, their functionalization terms density, fuel temperature, soluble poison concentration, were obtained input the NESTLE code. By predictions consistent methodologies NESTLE, when after All-Rods-Out (ARO) maximum reactivity power differences between 2 pcm 0.003 ARO simulations. For rodded simulations, grew 58 0.04. Increases determined be attributed usage unrodded points whether is partially or not, practice. Obtaining reduced powers.