Dr. Paul Van Uffelen graduated from the Vrije Universiteit Brussel (Belgium) and the Ecole
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …

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 …

Reactor structural integrity and nuclear safety are seriously affected by the fission gas
behaviors and relevant physical phenomena in nuclear fuels. In this review, the fission gas …

In this study, a number of samples of UN sintered by the SPS method have been fabricated,
and highly pure samples ranging in density from 68% to 99.8% TD–corresponding to an …

Abstract Design and safety assessment of fuel pins for application in innovative Generation
IV fast reactors calls for a dedicated nuclear fuel modelling and for the extension of the fuel …

Mechanistic multi-scale modelling holds the potential to inform fuel performance codes by
incorporating high-fidelity models, algorithms, parameters, and material properties. In this …

When assessing the radiological consequences of postulated accident scenarios, it is of
primary interest to determine the amount of radioactive fission gas accumulated in the fuel …

Uranium mononitride (UN) is a nuclear fuel candidate for advanced reactor designs and an
alternative being considered for light water reactors due to its higher thermal conductivity …

The goal of this deliverable is to present a synthesis of the model developments achieved
during the INSPYRE Project with respect to the description of inert gas (ie, helium and …

Under loss-of-coolant conditions, the temperature on fuel cladding will increase rapidly (up
to 1000–1500 K), which will not only cause a dramatic oxidation reaction of Zircaloy-4 and …