Abstract
This study summarises the work performed to introduce a novel methodology to derive the radial form factor in the TRANSURANUS burnup model (TUBRNP) using data from simulations. Previous work used experimental data from post-irradiation examinations to obtain the radial form factor in TUBRNP for a conventional LWR. It was updated to include coefficients suitable for a HWR. The aim of this work is the creation of a reactor-dependent methodology using data from a Monte Carlo code when experimental data are missing, but that is still in line with the previous work. This new TUBRNP model, together with recently implemented correlations for Hastelloy-N to be used as cladding and FliBe as coolant, provide an updated TRANSURANUS fuel rod performance code that can be used in ongoing investigations for AGR-like molten salt cooled reactors. The proposed methodology can also be applied to advanced technology fuels in various SMRs.
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