TY - JOUR

T1 - Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation

AU - Bertolus, Marjorie

AU - Freyss, Michel

AU - Dorado, Boris

AU - Martin, Guillaume

AU - Hoang, Kiet

AU - Maillard, Serge

AU - Skorek, Richard

AU - Garcia, Philippe

AU - Valot, Carole

AU - Chartier, Alain

AU - Van Brutzel, Laurent

AU - Fossati, Paul

AU - Grimes, Robin W.

AU - Parfitt, David C.

AU - Bishop, Clare L.

AU - Murphy, Samuel T.

AU - Rushton, Michael J. D.

AU - Staicu, Dragos

AU - Yakub, Eugen

AU - Nichenko, Sergii

AU - Krack, Matthias

AU - Devynck, Fabien

AU - Ngayam-Happy, Raoul

AU - Govers, Kevin

AU - Deo, Chaitanya S.

AU - Behera, Rakesh K.

PY - 2015/7/1

Y1 - 2015/7/1

N2 - This article presents a synthesis of the investigations at the atomic scale of the transport properties of defects and fission gases in uranium dioxide, as well as of the transfer of results from the atomic scale to models at the mesoscopic scale, performed during the F-BRIDGE European project (2008-2012). We first present the mesoscale models used to investigate uranium oxide fuel under irradiation, and in particular the cluster dynamics and kinetic Monte Carlo methods employed to model the behaviour of defects and fission gases in UO2, as well as the parameters of these models. Second, we describe briefly the atomic scale methods employed, i.e. electronic structure calculations and empirical potential methods. Then, we show the results of the calculation of the data necessary for the mesoscale models using these atomic scale methods. Finally, we summarise the links built between the atomic and mesoscopic scale by listing the data calculated at the atomic scale which are to be used as input in mesoscale modelling. Despite specific difficulties in the description of fuel materials, the results obtained in F-BRIDGE show that atomic scale modelling methods are now mature enough to obtain precise data to feed higher scale models and help interpret experiments on nuclear fuels. These methods bring valuable insight, in particular the formation, binding and migration energies of point and extended defects, fission product localization, incorporation energies and migration pathways, elementary mechanisms of irradiation induced processes. These studies open the way for the investigation of other significant phenomena involved in fuel behaviour, in particular the thermochemical and thermomechanical properties and their evolution in-pile, complex microstructures, as well as of more complex fuels. (C) 2015 Elsevier B.V. All rights reserved.

AB - This article presents a synthesis of the investigations at the atomic scale of the transport properties of defects and fission gases in uranium dioxide, as well as of the transfer of results from the atomic scale to models at the mesoscopic scale, performed during the F-BRIDGE European project (2008-2012). We first present the mesoscale models used to investigate uranium oxide fuel under irradiation, and in particular the cluster dynamics and kinetic Monte Carlo methods employed to model the behaviour of defects and fission gases in UO2, as well as the parameters of these models. Second, we describe briefly the atomic scale methods employed, i.e. electronic structure calculations and empirical potential methods. Then, we show the results of the calculation of the data necessary for the mesoscale models using these atomic scale methods. Finally, we summarise the links built between the atomic and mesoscopic scale by listing the data calculated at the atomic scale which are to be used as input in mesoscale modelling. Despite specific difficulties in the description of fuel materials, the results obtained in F-BRIDGE show that atomic scale modelling methods are now mature enough to obtain precise data to feed higher scale models and help interpret experiments on nuclear fuels. These methods bring valuable insight, in particular the formation, binding and migration energies of point and extended defects, fission product localization, incorporation energies and migration pathways, elementary mechanisms of irradiation induced processes. These studies open the way for the investigation of other significant phenomena involved in fuel behaviour, in particular the thermochemical and thermomechanical properties and their evolution in-pile, complex microstructures, as well as of more complex fuels. (C) 2015 Elsevier B.V. All rights reserved.

U2 - 10.1016/j.jnucmat.2015.02.026

DO - 10.1016/j.jnucmat.2015.02.026

M3 - Erthygl

VL - 462

SP - 475

EP - 495

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -