2-D and 3-D modelling of fission gas release due to intra-granular bubble movement during post-irradiation annealing of UO2 fuel (in session "Session 3")
3D-reconstruction via genetic algorithms: Application to metallic fuel (in session "Session 6")
A burn-up module for application in fuel performance codes: methodology, verification and assessment for MOX fuel in thermal and fast neutron spectra (in session "Session 2")
A DEM/FFT approach to compute the effective thermal conductivity of fragmented fuels under accident conditions (in session "Session 6")
A new laser heating setup for the measurement of noble gases diffusion in nuclear materials (in session "Poster flash talks")
Accelerated Testing of Fast Reactor Fuel in the Advanced Test Reactor (in session "Session 5")
Adaptive Kinetic Monte Carlo (AKMC) modelling of radiation defects in mixed oxide (MOX) fuel (in session "Poster flash talks")
Advances in phase-field modelling incorporating bulk thermodynamics and interfacial excess quantities (in session "Poster flash talks")
Analysis of fuel rod behavior during design basis accidents using the Bison code (in session "Session 2")
Assessment of the current European Fuel Performance Codes against the Fast Reactor irradiation experiment SUPERFACT (in session "Session 7")
Atomic scale modelling of stoichiometry deviation in amorphous zirconia (in session "Poster flash talks")
Dependence of molten salt liquidus temperature on its composition (in session "Session 11")
Design of a novel set-up for the investigation of helium behaviour in oxide nuclear fuel via infusion: realization, modelling and preliminary results (in session "Session 3")
Development and assessment of a mechanistic model describing high burnup structure behavior in oxide nuclear fuel (in session "Session 6")
Development and Implementation of a Thermochemical Database, MSTDB, for Simulating Fuel Behavior in Molten Salt Reactors (in session "Session 1")
Development of a thermo-kinetic model of cations in the mixed oxide of Uranium & Plutonium (in session "Session 7")
Development of the 3D Fuel Behaviour Code OFFBEAT (in session "Session 10")
Experimental investigation of the U-Zr-Fe-O liquid miscibility gap (in session "Session 8")
Experimental study of Joint-Oxyde-Gaine (JOG) systems in Fast Neutron Reactors (in session "Poster flash talks")
Final discussion (in session "Session 11")
Finite element modeling of fuel behavior based on the MOOSE framework (in session "Poster flash talks")
Fuel Thermomechanical modelling with Falcon at PSI (in session "Session 4")
GEMS / MELCOR coupling and its application to fission product release simulations (in session "Session 1")
High temperature interaction between UO2, steel and B4C in the frame of sodium fast reactor severe accident studies (in session "Session 8")
In-Pile Experiment Development to Investigate Transient Irradiation Performance of Fast Reactor Fuels at TREAT (in session "Session 5")
Interaction between sodium and nanosized mixed oxide fuel (U1-xPux)O2: focus on the structural characterization of Na4(U1-xPux)O5. (in session "Session 9")
Manufacture and modelling of advanced UB2 fuel (in session "Session 9")
Mesoscale fission gas percolation simulations of heterogeneous and irregular grain networks (in session "Session 6")
Microstructural evolution of Fe-9Cr alloys under 3.5 MeV Fe13+ ion irradiation (in session "Poster flash talks")
Microstructural investigation of (U,Pu)O2-x fuel by Raman spectroscopy (in session "Poster flash talks")
Modelling of the H2020 INSPYRE fuel creep experiment in HFR with TRANSURANUS (in session "Session 7")
Modernization of UO2 nuclear fuel (in session "Session 9")
Multi-scale nuclear fuel simulation with VER software (in session "Session 2")
Multiscale modelling of cracking in CeO2 and UO2 pellets (in session "Session 10")
New helium equation of state for pressurized nanobubbles in UO2 matrix calculated via molecular dynamics simulations (in session "Session 3")
New insight into the thermodynamic and atom transport properties of (U,Pu)O$_2$ nuclear fuel from atomic scale calculations (in session "Session 7")
Noble gas transport in UO2 annealed under controlled O2 partial pressure: first results (in session "Session 3")
Peridynamic Modelling of Nuclear Materials (in session "Session 10")
Physico-chemical properties of molten salt fuel: development of innovative techniques (in session "Session 8")
PLEIADES ALCYONE 3.5D simulation of a power ramp including OpenCalphad fuel thermochemistry with TAF-ID (in session "Session 2")
Postirradiation Examination on Innovative Advance Reactor Metallic Fuel Concepts (in session "Session 5")
Recent Development of Thermochimica for Simulations of Nuclear Materials (in session "Session 1")
Release of volatile fission products (Xe, Kr, I, Cs) implanted in polycrystalline UO2 (in session "Poster flash talks")
Simulation of pure and Cr-doped UO$_2$ using molecular dynamics and density functional theory (in session "Poster flash talks")
Sintering behaviours and microstructure analysis of UN-UO2 composite fuels prepared by spark plasma sintering (in session "Poster flash talks")
Steam oxidation of SiC at high temperatures studied by laser heating method (in session "Session 4")
Study of alpha self-irradiation on americium-doped uranium oxide (in session "Session 5")
The Changing Role of Computation in Material and Process Design (in session "Session 11")
Thermochemical Modeling In-Reactor Behavior of Uranium Silicide-Based Accident Tolerant Fuels (in session "Session 4")
Thermodynamic modelling of the U-Pu-Am-O system (in session "Poster flash talks")
Thermodynamic properties of Fe-Zr-O system at high temperatures (in session "Session 8")
Thermodynamic, Transport, and Structural Study of the LiF-UF4 System (in session "Session 1")
Towards improved measurement capabilities and better understanding of the thermo-physical properties of nuclear materials (in session "Session 10")
UO2 corrosion by liquid sodium (in session "Session 9")
Include materials from selected contributions
