Plutonium Management for More Agility

Informations projet

PUMMA

N° de convention de subvention: 945022

DOI

10.3030/945022

Projet clôturé

Date de signature de la CE 19 Mai 2020

Date de début 1 Octobre 2020

Date de fin 31 Mars 2025

Financé au titre de

• Euratom

Coût total

€ 6 729 994,19

Contribution de l’UE

€ 3 795 800,50

Coordonné par

COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
France

CORDIS fournit des liens vers les livrables publics et les publications des projets HORIZON.

Les liens vers les livrables et les publications des projets du 7e PC, ainsi que les liens vers certains types de résultats spécifiques tels que les jeux de données et les logiciels, sont récupérés dynamiquement sur OpenAIRE .

Livrables

Documents, reports (13)

Calculation of melting temperature with CALPHAD based on recent measurements

D3.3.1Calculation of melting temperature with CALPHAD based on recent measurements

State of the art on MOX thermal properties with atomic scale modelling. New calculations and requirements for new measurements

D3.1.1State of the art on MOX thermal properties with atomic scale modelling. New calculations and requirements for new measurements

Report on scenario calculations

D1.2.1Report on scenario calculations

Synthesis of the impact of the Pu management in the fuel cycle
"E&T materials: e-platform ""Wiki-FUEL"", MOOC"

D6.1.3 E&T materials: e-platform “Wiki-FUEL”, MOOC

Communication and Dissemination strategy action plan

D6.3.1 Communication and Dissemination strategy action plan

Co-ordination of Pu-active and HA dissolution experiments

D5.1.1Co-ordination of Pu-active and HA dissolution experiments

Comparison of MTR and FR fuel irradiation experiments for assessment of the validity of MTR irradiations for FR fuel qualifications.

D4.2.1Comparison of MTR and FR fuel irradiation experiments for assessment of the validity of MTR irradiations for FR fuel qualifications.

Project Quality Plan

D7.2.1Project Quality Plan

State of the art on MOX mechanical properties. Requirements on measurements of mechanical properties

D3.2.1State of the art on MOX mechanical properties. Requirements on measurements of mechanical properties

Communication toolbox: design flyer, set up website and create social media accounts

D6.4.1 Communication toolbox: design flyer, set up website and create social media accounts

Finite element modelling of fuel rod

D3.2.2Finite element modelling of fuel rod

Report on Impact of fuel cycle analysis in facilities and transport and economic evaluation

D1.4.1Report on Impact of fuel cycle analysis in facilities and transport and economic evaluation

Publications

Peer reviewed articles (10)

Modelling and assessment of thermophysical properties of Am-bearing fuels for transmutation purposes in fast reactors

Auteurs: M. Di Gennaro, A. Magni, M. Guarnieri, D. Pizzocri, L. Luzzi, C. Guéneau, P. Van Uffelen
Publié dans: Progress in Nuclear Energy, Numéro 185, 2025, Page(s) 105698, ISSN 0149-1970
Éditeur: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105698

PuMMA blind benchmark: Performance of high plutonium content MOX fuel under irradiation

Auteurs: D. Jaramillo-Sierra, M. Stefanowska-Skrodzka, J. Lavarenne, E. Deveaux, E. Brunetto, V. Matocha, A. Magni, K. Sturm, K. Mikityuk, Y. Wang, A. Jiménez-Carrascosa, J. Gado, B. Burger, V. Blanc, V. Dupont, L. Argeles, B. Perrin, G. Michel, A. Scolaro, C. Fiorina, J. Peltonen, A. Del Nevo, L. Luzzi, D. Pizzocri, S. Lemehov, S. Bebjak, T. Chrebet, C. Strmensky
Publié dans: Nuclear Engineering and Design, Numéro 435, 2025, Page(s) 113960, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.113960

ALFRED-burner: Core design, safety and performance

Auteurs: D. Jaramillo-Sierra, G. Grasso, E. Dorval, A. Magni, A. Cammi, A. Del Nevo
Publié dans: Nuclear Engineering and Design, Numéro 432, 2025, Page(s) 113826, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.113826

Multi-scale structural investigation of hypo-stoichiometric (U1-yPuy)O1.98 oxides with high plutonium content

Auteurs: M.-M. Desagulier, J. Martinez, P.M. Martin, F. Lebreton, M.O.J.Y. Hunault, C. Guéneau, N. Clavier
Publié dans: Journal of the European Ceramic Society, Numéro 45, 2025, Page(s) 117623, ISSN 0955-2219
Éditeur: Elsevier BV
DOI: 10.1016/j.jeurceramsoc.2025.117623

Thermodynamic and thermoelastic properties of hypostoichiometric MOX fuels with molecular dynamics simulations

Auteurs: G. Porto, J. Bouchet, D. Bathellier, J. Bodin, M. Canducci, J. Tranchida, P. Fossati, P. Martin, E. Bourasseau
Publié dans: Journal of Nuclear Materials, Numéro 598, 2025, Page(s) 155163, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2024.155163

Off-centering effects on MOX fuel behavior

Auteurs: D. Jaramillo-Sierra, V. Blanc, T. Barani, A. Cammi, A. Del Nevo
Publié dans: Nuclear Engineering and Design, Numéro 444, 2025, Page(s) 114372, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.114372

First Post Irradiation Examinations on a fast reactor grade MOX fuel (U0.6,Pu0.4)O2 for Pu-burning application, irradiated in the High Flux Reactor

Auteurs: S. van Til, A.V. Fedorov, F. Nindiyasari, F. Charpin-Jacobs, G. Uitslag, F. Pasti, E. D'Agata, N. Chauvin
Publié dans: Journal of Nuclear Materials, Numéro 608, 2025, Page(s) 155707, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2025.155707

Development of a dynamic-mesh porosity transport model for multi-dimensional fuel performance codes

Auteurs: Edoardo Luciano Brunetto, Carlo Fiorina, Andreas Pautz, Sander van Til, Fitriana Nindiyasari, Alexander Fedorov, Alessandro Scolaro
Publié dans: Journal of Nuclear Materials, Numéro 608, 2025, Page(s) 155717, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2025.155717

Effects of irradiation on the insolubility of sodium fast reactor (U,Pu)O2 mixed oxide with a very high amount of plutonium

Auteurs: Martin Giraud, Nathalie Reynier-Tronche, Emilie Buravand
Publié dans: Journal of Nuclear Materials, 2023, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154727

Multi-scale structural investigation of uranium-plutonium mixed oxides (U1-yPuy)O2-x with high plutonium content

Auteurs: M-M. Desagulier a, J. Martinez a, P.M. Martin a, F. Lebreton a, C. Guéneau b, N. Clavier c
Publié dans: Journal of Nuclear Materials, 2023, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154645