Development of a robust, accurate and efficient coupling between PLEIADES/ALCYONE 2.1 fuel performance code and the OpenCalphad thermo-chemical solver

3D simulation of a power ramp including fuel thermochemistry and oxygen thermodiffusion

(2019) P. Konarski et al.   JOURNAL OF NUCLEAR MATERIALS

Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident

(2019) E. Geiger et al.   JOURNAL OF NUCLEAR MATERIALS

Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment

(2017) B. Michel et al.   NUCLEAR TECHNOLOGY

Modelling of liquid phase segregation in the Uranium–Oxygen binary system

(2016) C. Cardon et al.   CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY

Global optimization algorithms to compute thermodynamic equilibria in large complex systems with performance considerations

(2016) M.H.A. Piro et al.   COMPUTATIONAL MATERIALS SCIENCE

Experimental evidence of oxygen thermo-migration in PWR UO 2 fuels during power ramps using in-situ oxido-reduction indicators

(2016) Ch. Riglet-Martial et al.   JOURNAL OF NUCLEAR MATERIALS

Thermochemical modeling of nuclear fuel and the effects of oxygen potential buffers

(2016) Henri Loukusa et al.   JOURNAL OF NUCLEAR MATERIALS

The implementation of an algorithm to calculate thermodynamic equilibria for multi-component systems with non-ideal phases in a free software

(2015) Bo Sundman et al.   COMPUTATIONAL MATERIALS SCIENCE

Iterative residual-based vector methods to accelerate fixed point iterations

(2015) Isabelle Ramière et al.   COMPUTERS & MATHEMATICS WITH APPLICATIONS

3D thermo-chemical–mechanical simulation of power ramps with ALCYONE fuel code

(2014) B. Baurens et al.   JOURNAL OF NUCLEAR MATERIALS

Evidence of tellurium iodide compounds in a power-ramped irradiated UO2 fuel rod

(2013) L. Desgranges et al.   JOURNAL OF NUCLEAR MATERIALS

Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO2 nuclear fuel

(2013) M.H.A. Piro et al.   JOURNAL OF NUCLEAR MATERIALS

Performance enhancing algorithms for computing thermodynamic equilibria

(2012) M.H.A. Piro et al.   CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY

Numerical verification of equilibrium thermodynamic computations in nuclear fuel performance codes

(2011) M.H.A. Piro et al.   JOURNAL OF NUCLEAR MATERIALS

Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems

(2011) Christine Guéneau et al.   JOURNAL OF NUCLEAR MATERIALS

MARGARET: A comprehensive code for the description of fission gas behavior

(2011) L. Noirot   NUCLEAR ENGINEERING AND DESIGN

Power ramped cladding stresses and strains in 3D simulations with burnup-dependent pellet–clad friction

(2011) J. Sercombe et al.   NUCLEAR ENGINEERING AND DESIGN