Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests

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

(2020) C. Introïni et al.   NUCLEAR ENGINEERING AND DESIGN

TAF-ID: An international thermodynamic database for nuclear fuels applications

(2020) C. Guéneau et al.   CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY

New insights into the Cs-Mo-O system: Experimental studies of the Cs2MoO4-MoO3 pseudo-binary system

(2020) A.L. Smith et al.   THERMOCHIMICA ACTA

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

Contribution to the thermodynamic description of the corium – The U-Zr-O system

(2018) A. Quaini et al.   JOURNAL OF NUCLEAR MATERIALS

Fission products and nuclear fuel behaviour under severe accident conditions part 3: Speciation of fission products in the VERDON-1 sample

(2017) C. Le Gall et al.   JOURNAL OF NUCLEAR MATERIALS

Fission products and nuclear fuel behaviour under severe accident conditions part 2: Fuel behaviour in the VERDON-1 sample

(2017) E. Geiger et al.   JOURNAL OF NUCLEAR MATERIALS

Fission products and nuclear fuel behaviour under severe accident conditions part 1: Main lessons learnt from the first VERDON test

(2017) Y. Pontillon 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

The OpenCalphad thermodynamic software interface

(2016) Bo Sundman et al.   COMPUTATIONAL MATERIALS SCIENCE

On the interpretation of chemical potentials computed from equilibrium thermodynamic codes

(2015) M.H.A. Piro et al.   JOURNAL OF NUCLEAR MATERIALS

Performance and first results of fission product release and transport provided by the VERDON facility

(2014) A. Gallais-During et al.   NUCLEAR ENGINEERING AND DESIGN

Fission product release from nuclear fuel I. Physical modelling in the ASTEC code

(2013) G. Brillant et al.   ANNALS OF NUCLEAR ENERGY

Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis

(2013) Giovanni Pastore et al.   NUCLEAR ENGINEERING AND DESIGN

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

A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code

(2011) G. Khvostov et al.   NUCLEAR ENGINEERING AND DESIGN

Behaviour of fission products under severe PWR accident conditions VERCORS experimental programme—Part 1: General description of the programme

(2009) Yves Pontillon et al.   NUCLEAR ENGINEERING AND DESIGN

Behaviour of fission products under severe PWR accident conditions. The VERCORS experimental programme—Part 3: Release of low-volatile fission products and actinides

(2009) Yves Pontillon et al.   NUCLEAR ENGINEERING AND DESIGN

Behaviour of fission products under severe PWR accident conditions

(2009) Yves Pontillon et al.   NUCLEAR ENGINEERING AND DESIGN

New modelling of the U–O–Zr phase diagram in the hyper-stoichiometric region and consequences for the fuel rod liquefaction in oxidising conditions

(2008) M. Barrachin et al.   JOURNAL OF NUCLEAR MATERIALS

3D fuel cracking modelling in pellet cladding mechanical interaction

(2007) B. Michel et al.   ENGINEERING FRACTURE MECHANICS