Plutonium Management for More Agility

Informazioni relative al progetto

PUMMA

ID dell’accordo di sovvenzione: 945022

DOI

10.3030/945022

Progetto chiuso

Data della firma CE 19 Maggio 2020

Data di avvio 1 Ottobre 2020

Data di completamento 31 Marzo 2025

Finanziato da

• Euratom

Costo totale

€ 6 729 994,19

Contributo UE

€ 3 795 800,50

Coordinato da

COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
France

CORDIS fornisce collegamenti ai risultati finali pubblici e alle pubblicazioni dei progetti ORIZZONTE.

I link ai risultati e alle pubblicazioni dei progetti del 7° PQ, così come i link ad alcuni tipi di risultati specifici come dataset e software, sono recuperati dinamicamente da .OpenAIRE .

Risultati finali

Documents, reports (12)

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

Pubblicazioni

Peer reviewed articles (10)

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

Autori: M. Di Gennaro, A. Magni, M. Guarnieri, D. Pizzocri, L. Luzzi, C. Guéneau, P. Van Uffelen
Pubblicato in: Progress in Nuclear Energy, Numero 185, 2025, Pagina/e 105698, ISSN 0149-1970
Editore: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105698

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

Autori: 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
Pubblicato in: Nuclear Engineering and Design, Numero 435, 2025, Pagina/e 113960, ISSN 0029-5493
Editore: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.113960

ALFRED-burner: Core design, safety and performance

Autori: D. Jaramillo-Sierra, G. Grasso, E. Dorval, A. Magni, A. Cammi, A. Del Nevo
Pubblicato in: Nuclear Engineering and Design, Numero 432, 2025, Pagina/e 113826, ISSN 0029-5493
Editore: 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

Autori: M.-M. Desagulier, J. Martinez, P.M. Martin, F. Lebreton, M.O.J.Y. Hunault, C. Guéneau, N. Clavier
Pubblicato in: Journal of the European Ceramic Society, Numero 45, 2025, Pagina/e 117623, ISSN 0955-2219
Editore: Elsevier BV
DOI: 10.1016/j.jeurceramsoc.2025.117623

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

Autori: G. Porto, J. Bouchet, D. Bathellier, J. Bodin, M. Canducci, J. Tranchida, P. Fossati, P. Martin, E. Bourasseau
Pubblicato in: Journal of Nuclear Materials, Numero 598, 2025, Pagina/e 155163, ISSN 0022-3115
Editore: Elsevier BV
DOI: 10.1016/j.jnucmat.2024.155163

Off-centering effects on MOX fuel behavior

Autori: D. Jaramillo-Sierra, V. Blanc, T. Barani, A. Cammi, A. Del Nevo
Pubblicato in: Nuclear Engineering and Design, Numero 444, 2025, Pagina/e 114372, ISSN 0029-5493
Editore: 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

Autori: S. van Til, A.V. Fedorov, F. Nindiyasari, F. Charpin-Jacobs, G. Uitslag, F. Pasti, E. D'Agata, N. Chauvin
Pubblicato in: Journal of Nuclear Materials, Numero 608, 2025, Pagina/e 155707, ISSN 0022-3115
Editore: Elsevier BV
DOI: 10.1016/j.jnucmat.2025.155707

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

Autori: Edoardo Luciano Brunetto, Carlo Fiorina, Andreas Pautz, Sander van Til, Fitriana Nindiyasari, Alexander Fedorov, Alessandro Scolaro
Pubblicato in: Journal of Nuclear Materials, Numero 608, 2025, Pagina/e 155717, ISSN 0022-3115
Editore: 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

Autori: Martin Giraud, Nathalie Reynier-Tronche, Emilie Buravand
Pubblicato in: Journal of Nuclear Materials, 2023, ISSN 0022-3115
Editore: 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

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