There is an inevitable uncertainty in the coupled neutronic/thermal-hydraulic calculations, which are used for simulating the performance of nuclear reactors, due to the influence of design parameters and initial conditions. The application of uncertainty analysis methods in such calculations can reduce the "uncertainty zone" of calculation results as well as the unnecessary safety margin of the reactor. In this study, based on the combination of user-defined function (UDF) of FLUENT, a computational fluid dynamics (CFD) code, with the neutron dynamics model, fuel pin heat transfer model, and ...
