Gaseous fission product generation, transport, and release can have a large impact on
nuclear fuel performance, degrading fuel and fuel–cladding gap properties. Over the past …

A physics-based model is developed for analysing the coupled phenomena of fission gas
swelling and release in UO2 fuel during irradiation. The model is featured by a level of …

The role of uncertainties in fission gas behavior calculations as part of engineering-scale
nuclear fuel modeling is investigated using the BISON fuel performance code with a recently …

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 …

TRANSURANUS is a computer program for the thermal and mechanical analysis of fuel rods
irradiated in nuclear reactors. It was originally developed at the Institute for Transuranium …

The description of intra-granular fission gas behaviour is a fundamental part of any model for
the prediction of fission gas release and swelling in nuclear fuel. In this work we present a …

Fission gas release and gaseous swelling in nuclear fuel are driven by the transport of
fission gas from within the fuel grains to grain boundaries (intra-granular fission gas …

In the framework of long term behaviour of nuclear spent fuels, the performance codes need
physical data base such as fission gas equation of state in order to assess the pressure …

Abstract UO 2 samples doped with 0.1 wt.% plutonium oxide have been investigated with
the aim to study alpha-damage effects and the behaviour of radiogenic helium in spent …