Plutonium Management for More Agility

Projektinformationen

PUMMA

ID Finanzhilfevereinbarung: 945022

DOI

10.3030/945022

Projekt abgeschlossen

EK-Unterschriftsdatum 19 Mai 2020

Startdatum 1 Oktober 2020

Enddatum 31 März 2025

Finanziert unter

• Euratom

Gesamtkosten

€ 6 729 994,19

EU-Beitrag

€ 3 795 800,50

Koordiniert durch

COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
France

CORDIS bietet Links zu öffentlichen Ergebnissen und Veröffentlichungen von HORIZONT-Projekten.

Links zu Ergebnissen und Veröffentlichungen von RP7-Projekten sowie Links zu einigen Typen spezifischer Ergebnisse wie Datensätzen und Software werden dynamisch von OpenAIRE abgerufen.

Leistungen

Documents, reports (16)

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

Effect of burn up and uncertainties on the melting temperature

D3.3.2Effect of burn up and uncertainties on the melting temperature

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

Workshops report

D6.2.1 Workshops report

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

Comparison of MTR and FR core characteristics and related fuel pin performance

D4.1.1Comparison of MTR and FR core characteristics and related fuel pin performance

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

Veröffentlichungen

Peer reviewed articles (10)

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

Autoren: M. Di Gennaro, A. Magni, M. Guarnieri, D. Pizzocri, L. Luzzi, C. Guéneau, P. Van Uffelen
Veröffentlicht in: Progress in Nuclear Energy, Ausgabe 185, 2025, Seite(n) 105698, ISSN 0149-1970
Herausgeber: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105698

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

Autoren: 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
Veröffentlicht in: Nuclear Engineering and Design, Ausgabe 435, 2025, Seite(n) 113960, ISSN 0029-5493
Herausgeber: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.113960

ALFRED-burner: Core design, safety and performance

Autoren: D. Jaramillo-Sierra, G. Grasso, E. Dorval, A. Magni, A. Cammi, A. Del Nevo
Veröffentlicht in: Nuclear Engineering and Design, Ausgabe 432, 2025, Seite(n) 113826, ISSN 0029-5493
Herausgeber: 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

Autoren: M.-M. Desagulier, J. Martinez, P.M. Martin, F. Lebreton, M.O.J.Y. Hunault, C. Guéneau, N. Clavier
Veröffentlicht in: Journal of the European Ceramic Society, Ausgabe 45, 2025, Seite(n) 117623, ISSN 0955-2219
Herausgeber: Elsevier BV
DOI: 10.1016/j.jeurceramsoc.2025.117623

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

Autoren: G. Porto, J. Bouchet, D. Bathellier, J. Bodin, M. Canducci, J. Tranchida, P. Fossati, P. Martin, E. Bourasseau
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 598, 2025, Seite(n) 155163, ISSN 0022-3115
Herausgeber: Elsevier BV
DOI: 10.1016/j.jnucmat.2024.155163

Off-centering effects on MOX fuel behavior

Autoren: D. Jaramillo-Sierra, V. Blanc, T. Barani, A. Cammi, A. Del Nevo
Veröffentlicht in: Nuclear Engineering and Design, Ausgabe 444, 2025, Seite(n) 114372, ISSN 0029-5493
Herausgeber: 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

Autoren: S. van Til, A.V. Fedorov, F. Nindiyasari, F. Charpin-Jacobs, G. Uitslag, F. Pasti, E. D'Agata, N. Chauvin
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 608, 2025, Seite(n) 155707, ISSN 0022-3115
Herausgeber: Elsevier BV
DOI: 10.1016/j.jnucmat.2025.155707

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

Autoren: Edoardo Luciano Brunetto, Carlo Fiorina, Andreas Pautz, Sander van Til, Fitriana Nindiyasari, Alexander Fedorov, Alessandro Scolaro
Veröffentlicht in: Journal of Nuclear Materials, Ausgabe 608, 2025, Seite(n) 155717, ISSN 0022-3115
Herausgeber: 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

Autoren: Martin Giraud, Nathalie Reynier-Tronche, Emilie Buravand
Veröffentlicht in: Journal of Nuclear Materials, 2023, ISSN 0022-3115
Herausgeber: 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

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