Plutonium Management for More Agility

Project Information

PUMMA

Grant agreement ID: 945022

DOI

10.3030/945022

Project closed

EC signature date 19 May 2020

Start date 1 October 2020

End date 31 March 2025

Funded under

• Euratom

Total cost

€ 6 729 994,19

EU contribution

€ 3 795 800,50

Coordinated by

COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
France

CORDIS provides links to public deliverables and publications of HORIZON projects.

Links to deliverables and publications from FP7 projects, as well as links to some specific result types such as dataset and software, are dynamically retrieved from OpenAIRE .

Deliverables

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

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

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

Author(s): 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
Published in: Nuclear Engineering and Design, Issue 435, 2025, Page(s) 113960, ISSN 0029-5493
Publisher: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.113960

ALFRED-burner: Core design, safety and performance

Author(s): D. Jaramillo-Sierra, G. Grasso, E. Dorval, A. Magni, A. Cammi, A. Del Nevo
Published in: Nuclear Engineering and Design, Issue 432, 2025, Page(s) 113826, ISSN 0029-5493
Publisher: 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

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

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

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

Off-centering effects on MOX fuel behavior

Author(s): D. Jaramillo-Sierra, V. Blanc, T. Barani, A. Cammi, A. Del Nevo
Published in: Nuclear Engineering and Design, Issue 444, 2025, Page(s) 114372, ISSN 0029-5493
Publisher: 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

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

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

Author(s): Edoardo Luciano Brunetto, Carlo Fiorina, Andreas Pautz, Sander van Til, Fitriana Nindiyasari, Alexander Fedorov, Alessandro Scolaro
Published in: Journal of Nuclear Materials, Issue 608, 2025, Page(s) 155717, ISSN 0022-3115
Publisher: 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

Author(s): Martin Giraud, Nathalie Reynier-Tronche, Emilie Buravand
Published in: Journal of Nuclear Materials, 2023, ISSN 0022-3115
Publisher: 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

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