Bridging lower length-scale calculations with the engineering-scale simulations of fuel
performance codes requires the development of dedicated intermediate-scale codes. In this …

SCIANTIX is a 0D, open-source code designed to model inert gas behaviour within nuclear
fuel at the scale of the grain. The code predominantly employs mechanistic approaches …

The PLEIADES software environment is a simulation framework allowing the development of
fuel performance codes dedicated to specific nuclear systems (PWR, SFR, and material …

The description of intra-granular fission gas behavior during irradiation is a fundamental part
of models used for the calculation of fission gas release and gaseous swelling in nuclear …

The behavior of fission gas is a key issue for the performance of UO 2 fuel, which is the most
widely used fuel type in GEN-III reactors. Fission gas will lead to lower thermal conductivity …

This paper presents simulations of the VERDON 1 and RT6 tests (temperature increase up
to fuel-clad melting, oxidizing and/or reducing conditions within the furnace) performed with …

The ALCYONE multidimensional fuel performance code codeveloped by the CEA, EDF, and
AREVA NP within the PLEIADES software environment models the behavior of fuel rods …

In this article, a review of Pellet Cladding Interaction models is proposed. The key elements
behind the modeling stress-strain and iodine concentration at the clad inner wall during a …

The time-evolution of an intergranular bubble population is considered using the Included
Phase Model (IPM). The model considers the generation and coupled transport of vacancies …

Besides recent progresses in the physics-based modelling of fission gas and helium
behaviour, the scarcity of experimental data concerning their combined behaviour (ie …