Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software

Abstract

Features and capabilities of the SUN BPSD module for assessing the error in fuel burnup calculations due to the uncertainty of nuclear data and reactor plant process parameters, as well as fuel irradiation conditions, are described. Using the SUN module, two different methods for estimating the uncertainty of irradiated fuel characteristics were implemented. The post-reactor studies of fuel rods irradiated in a BN-350 reactor with mixed uranium-plutonium oxide fuel were considered as a demonstration calculation test using the SUN module.