Uncertainty analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations

The Best Estimate analysis consists of a coupled thermal-hydraulic and neutronic description of the nuclear system’s behavior; uncertainties from both aspects should be included and jointly propagated. This paper presents a study of the influence of the uncertainty in the macroscopic neutronic information that describes a three-dimensional core model on the most relevant results of the simulation of a Reactivity Induced Accident (RIA). The analyses of a BWR-RIA and a PWR-RIA have been carried out with a three-dimensional thermalhydraulic and neutronic model for the coupled system TRACE-PARCS and RELAP-PARCS.

کلیدواژه های Uncertainty analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations:

Uncertainty analysis ، Neutronic parameters ، BWR ، PWR