The role of dry storage in spent nuclear fuel management becomes more and more
important. Originally intended to serve as a temporary solution for a few decades until final …

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 …

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 …

Scandium trifluoride is a model negative thermal expansion (NTE) material. Its simple
structure can be described as an A-site vacant perovskite, and it shows isotropic NTE over a …

In this work, we propose a new mechanistic model for the treatment of helium behaviour
which includes the description of helium solubility in oxide fuel. The proposed model has …

In this work, we propose a new mechanistic model for the treatment of helium behaviour at
the grain boundaries in oxide nuclear fuel. The model provides a rate-theory description of …

In this study, silicon oxycarbide (SiOC) was fabricated by pyrolysis of a polysiloxane
precursor at 1000° C and 1500° C in an Ar atmosphere and evaluated as a new nuclear fuel …

The defect double perovskite [He2–x□ x][CaNb] F6, with helium on its A-site, can be
prepared by the insertion of helium into ReO3-type CaNbF6 at high pressure. Upon cooling …

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 …