Investigations Supporting MOX Fuel Licensing in ESNII Prototype Reactors

Deliverables

Documents, reports (20)

Report on the calculation of heat capacity vs. composition and stoichiometry

1st Newsletter

Report describing the results of the benchmark between improved codes and previous versions on selected irradiation experimental cases

Report on the review of available models and progress on the sub-models dealing with the intra- and intergranular inert gas behaviour

Report on simulations of mechanical properties of MOX under irradiation

Synthesis and assessment report on exchanges

3rd Newsletter

Report on the development of thermo-kinetic models and on the mobility database

Report on the improved models of melting temperature and thermal conductivity for MOX fuels and JOG

Report on new experimental results and on the mechanisms specific to FBR fuel thermal conductivity

Report on the fission gas and He behaviour in UO2

Synthesis of the first user group meeting

Report describing the complete inert gas behaviour model with grain re-crystallization and the corresponding improved data

Report describing the incorporation and verification of models and properties in TRANSURANUS, MACROS/TRANSURANUS and GERMINAL

Report describing the irradiation experiments selected for the assessment of fuel performance codes

2nd Newsletter

Report on the CALPHAD optimisation of (U-Pu-Am-O) phase diagrams

Synthesis of first meeting with the Scientific Advisory Committee

Report on results of the applicative benchmark between TRANSURANUS and GERMINAL

New correlations of thermal expansion and Young's modulus based on existing literature and new data

Publications

Peer reviewed articles (16)

Study of thermodynamic properties of U1-yPuyO2 MOX fuel using classical molecular Monte Carlo simulations

Author(s): Cyrille Takoukam-Takoundjou, Emeric Bourasseau, Véronique Lachet
Published in: Journal of Nuclear Materials, 534, 2020, Page(s) 152125, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/j.jnucmat.2020.152125

Electron polarons and donor point defects in americium dioxide AmO 2

Author(s): Martin Talla Noutack, Michel Freyss, Gérald Jomard, Grégory Geneste
Published in: Physical Review B: Condensed Matter and Materials Physics, 101, 2020, ISSN 1098-0121
Publisher: American Physical Society
DOI: 10.1103/physrevb.101.024108

Changes in voids induced by ion irradiations in UO2: In situ TEM studies

Author(s): C. Onofri, C. Sabathier, G. Carlot, D. Drouan, C. Bachelet, C. Baumier, M. Gérardin, M. Bricout
Published in: Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 463, 2020, Page(s) 76-85, ISSN 0168-583X
Publisher: Elsevier BV
DOI: 10.1016/j.nimb.2019.11.031

Structural, electronic and energetic properties of uranium–americium mixed oxides ${\rm U}_{1-y}{\rm Am}_y{\rm O}_2$ using DFT$+{U}$ calculations

Author(s): Martin S. Talla Noutack, Gérald Jomard, Michel Freyss, Grégory Geneste
Published in: Journal of Physics: Condensed Matter, 31/48, 2019, Page(s) 485501, ISSN 0953-8984
Publisher: Institute of Physics Publishing
DOI: 10.1088/1361-648x/ab395e

Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients

Author(s): T. Barani, G. Pastore, A. Magni, D. Pizzocri, P. Van Uffelen, L. Luzzi
Published in: Journal of Nuclear Materials, 538, 2020, Page(s) 152195, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/j.jnucmat.2020.152195

The effect of oxygen partial pressure on dislocation creep in polycrystalline uranium dioxide

Author(s): Philippe Garcia, Audrey Miard, Thomas Helfer, Jean-Baptiste Parise, Xavière Iltis, Guy Antou
Published in: Journal of the European Ceramic Society, 2020, ISSN 0955-2219
Publisher: Elsevier BV
DOI: 10.1016/j.jeurceramsoc.2020.09.005

Radiation effects in alpha-doped UO2

Author(s): E. De Bona, A. Benedetti, O. Dieste, D. Staicu, T. Wiss, R.J.M. Konings
Published in: Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 468, 2020, Page(s) 54-59, ISSN 0168-583X
Publisher: Elsevier BV
DOI: 10.1016/j.nimb.2020.01.024

A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools

Author(s): D. Pizzocri, G. Pastore, T. Barani, A. Magni, L. Luzzi, P. Van Uffelen, S.A. Pitts, A. Alfonsi, J.D. Hales
Published in: Journal of Nuclear Materials, 502, 2018, Page(s) 323-330, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/j.jnucmat.2018.02.024

Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations

Author(s): L. Luzzi, L. Cognini, D. Pizzocri, T. Barani, G. Pastore, A. Schubert, T. Wiss, P. Van Uffelen
Published in: Nuclear Engineering and Design, 330, 2018, Page(s) 265-271, ISSN 0029-5493
Publisher: Elsevier BV
DOI: 10.1016/j.nucengdes.2018.01.044

Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant

Author(s): L. Cognini, D. Pizzocri, T. Barani, P. Van Uffelen, A. Schubert, T. Wiss, L. Luzzi
Published in: Nuclear Engineering and Design, 340, 2018, Page(s) 240-244, ISSN 0029-5493
Publisher: Elsevier BV
DOI: 10.1016/j.nucengdes.2018.09.024

Influence of exogenous xenon atoms on the evolution kinetics of extended defects in polycrystalline UO2 using in situ TEM

Author(s): C. Onofri, C. Sabathier, C. Baumier, C. Bachelet, H. Palancher, B. Warot-Fonrose, M. Legros
Published in: Journal of Nuclear Materials, 512, 2018, Page(s) 297-306, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/j.jnucmat.2018.10.025

Electronic Structure Investigation of the Bulk Properties of Uranium–Plutonium Mixed Oxides (U, Pu)O 2

Author(s): Ibrahim Cheik Njifon, Marjorie Bertolus, Roland Hayn, Michel Freyss
Published in: Inorganic Chemistry, 57/17, 2018, Page(s) 10974-10983, ISSN 0020-1669
Publisher: American Chemical Society
DOI: 10.1021/acs.inorgchem.8b01561

Damage characterization of (U,Pu)O2 under irradiation by molecular dynamics simulations

Author(s): Hector Balboa, Laurent Van Brutzel, Alain Chartier, Yann Le Bouar
Published in: Journal of Nuclear Materials, 512, 2018, Page(s) 440-449, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/j.jnucmat.2018.07.056

An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution

Author(s): G. Pastore, D. Pizzocri, C. Rabiti, T. Barani, P. Van Uffelen, L. Luzzi
Published in: Journal of Nuclear Materials, 509, 2018, Page(s) 687-699, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/j.jnucmat.2018.07.030

SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes

Author(s): D. Pizzocri, T. Barani, L. Luzzi
Published in: Journal of Nuclear Materials, 532, 2020, Page(s) 152042, ISSN 0022-3115
Publisher: Elsevier BV
DOI: 10.1016/j.jnucmat.2020.152042

Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes

Author(s): L. Cognini, A. Cechet, T. Barani, D. Pizzocri, P. Van Uffelen, L. Luzzi
Published in: Nuclear Engineering and Technology, 2020, ISSN 1738-5733
Publisher: Korean Nuclear Society
DOI: 10.1016/j.net.2020.07.009