Fission gas release from UO2 nuclear fuel: A review
J Rest, MWD Cooper, J Spino, JA Turnbull… - Journal of Nuclear …, 2019 - Elsevier
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 …
nuclear fuel performance, degrading fuel and fuel–cladding gap properties. Over the past …
Burnable absorbers in nuclear reactors–a review
Burnable absorbers can benefit nuclear reactors of virtually any design by providing
reactivity control for extended fuel cycles, tritium production, burning of long-lived …
reactivity control for extended fuel cycles, tritium production, burning of long-lived …
[HTML][HTML] SCIANTIX: a new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes
D Pizzocri, T Barani, L Luzzi - Journal of Nuclear Materials, 2020 - Elsevier
Bridging lower length-scale calculations with the engineering-scale simulations of fuel
performance codes requires the development of dedicated intermediate-scale codes. In this …
performance codes requires the development of dedicated intermediate-scale codes. In this …
The TRANSURANUS fuel performance code
A Magni, A Del Nevo, L Luzzi, D Rozzia… - Nuclear Power Plant …, 2021 - Elsevier
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 …
irradiated in nuclear reactors. It was originally developed at the Institute for Transuranium …
[HTML][HTML] Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F
G Zullo, D Pizzocri, L Luzzi, F Kremer, R Dubourg… - Annals of Nuclear …, 2023 - Elsevier
Among the applications of the multiscale modelling approach in nuclear fuel rod
performance, the coupling of integral thermo-mechanical fuel performance codes with lower …
performance, the coupling of integral thermo-mechanical fuel performance codes with lower …
Modeling mesoscale fission gas behavior in UO2 by directly coupling the phase field method to spatially resolved cluster dynamics
Fission gas release within uranium dioxide nuclear fuel occurs as gas atoms diffuse through
grains and arrive at grain boundary (GB) bubbles; these GB bubbles grow and interconnect …
grains and arrive at grain boundary (GB) bubbles; these GB bubbles grow and interconnect …
Characterization of the radial microstructural evolution in LWR UO2 using electron backscatter diffraction
C McKinney, R Seibert, J Werden, C Parish… - Journal of Nuclear …, 2023 - Elsevier
Studies on high burnup UO 2 subjected to loss-of-coolant accident conditions have shown
that restructured regions of the fuel are susceptible to pulverization and eventual dispersal …
that restructured regions of the fuel are susceptible to pulverization and eventual dispersal …
Phase-field modeling of fission gas bubble growth on grain boundaries and triple junctions in UO2 nuclear fuel
A phase-field model of fission gas bubble evolution was developed and applied to gain an
improved understanding of the microstructure-level processes leading to fission gas release …
improved understanding of the microstructure-level processes leading to fission gas release …
Helium bubbles diffusion in aluminum: Influence of gas pressure
A Antropov, V Stegailov - Journal of Nuclear Materials, 2023 - Elsevier
The influence of helium pressure on the mechanisms of diffusion of the He-filled
nanobubbles in fcc Al is investigated by the classical molecular dynamics. It is shown that at …
nanobubbles in fcc Al is investigated by the classical molecular dynamics. It is shown that at …
Incorporation of Kr and Xe in uranium mononitride: a density functional theory study
L Yang, N Kaltsoyannis - The Journal of Physical Chemistry C, 2021 - ACS Publications
Uranium nitride is a material of considerable fundamental interest and is a promising
candidate for an advanced nuclear fuel. We here study intrinsic point defects and …
candidate for an advanced nuclear fuel. We here study intrinsic point defects and …