Plutonium Management for More Agility

Información del proyecto

PUMMA

Identificador del acuerdo de subvención: 945022

DOI

10.3030/945022

Proyecto cerrado

Fecha de la firma de la CE 19 Mayo 2020

Fecha de inicio 1 Octubre 2020

Fecha de finalización 31 Marzo 2025

Financiado con arreglo a

• Euratom

Coste total

€ 6 729 994,19

Aportación de la UE

€ 3 795 800,50

Coordinado por

COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
France

CORDIS proporciona enlaces a los documentos públicos y las publicaciones de los proyectos de los programas marco HORIZONTE.

Los enlaces a los documentos y las publicaciones de los proyectos del Séptimo Programa Marco, así como los enlaces a algunos tipos de resultados específicos, como conjuntos de datos y «software», se obtienen dinámicamente de OpenAIRE .

Resultado final

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

Publicaciones

Peer reviewed articles (10)

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

Autores: M. Di Gennaro, A. Magni, M. Guarnieri, D. Pizzocri, L. Luzzi, C. Guéneau, P. Van Uffelen
Publicado en: Progress in Nuclear Energy, Edición 185, 2025, Página(s) 105698, ISSN 0149-1970
Editor: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105698

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

Autores: 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
Publicado en: Nuclear Engineering and Design, Edición 435, 2025, Página(s) 113960, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.113960

ALFRED-burner: Core design, safety and performance

Autores: D. Jaramillo-Sierra, G. Grasso, E. Dorval, A. Magni, A. Cammi, A. Del Nevo
Publicado en: Nuclear Engineering and Design, Edición 432, 2025, Página(s) 113826, ISSN 0029-5493
Editor: 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

Autores: M.-M. Desagulier, J. Martinez, P.M. Martin, F. Lebreton, M.O.J.Y. Hunault, C. Guéneau, N. Clavier
Publicado en: Journal of the European Ceramic Society, Edición 45, 2025, Página(s) 117623, ISSN 0955-2219
Editor: Elsevier BV
DOI: 10.1016/j.jeurceramsoc.2025.117623

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

Autores: G. Porto, J. Bouchet, D. Bathellier, J. Bodin, M. Canducci, J. Tranchida, P. Fossati, P. Martin, E. Bourasseau
Publicado en: Journal of Nuclear Materials, Edición 598, 2025, Página(s) 155163, ISSN 0022-3115
Editor: Elsevier BV
DOI: 10.1016/j.jnucmat.2024.155163

Off-centering effects on MOX fuel behavior

Autores: D. Jaramillo-Sierra, V. Blanc, T. Barani, A. Cammi, A. Del Nevo
Publicado en: Nuclear Engineering and Design, Edición 444, 2025, Página(s) 114372, ISSN 0029-5493
Editor: 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

Autores: S. van Til, A.V. Fedorov, F. Nindiyasari, F. Charpin-Jacobs, G. Uitslag, F. Pasti, E. D'Agata, N. Chauvin
Publicado en: Journal of Nuclear Materials, Edición 608, 2025, Página(s) 155707, ISSN 0022-3115
Editor: Elsevier BV
DOI: 10.1016/j.jnucmat.2025.155707

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

Autores: Edoardo Luciano Brunetto, Carlo Fiorina, Andreas Pautz, Sander van Til, Fitriana Nindiyasari, Alexander Fedorov, Alessandro Scolaro
Publicado en: Journal of Nuclear Materials, Edición 608, 2025, Página(s) 155717, ISSN 0022-3115
Editor: 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

Autores: Martin Giraud, Nathalie Reynier-Tronche, Emilie Buravand
Publicado en: Journal of Nuclear Materials, 2023, ISSN 0022-3115
Editor: 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

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