Plutonium Management for More Agility

Informacje na temat projektu

PUMMA

Identyfikator umowy o grant: 945022

DOI

10.3030/945022

Projekt został zamknięty

Data podpisania przez KE 19 Maja 2020

Data rozpoczęcia 1 Października 2020

Data zakończenia 31 Marca 2025

Finansowanie w ramach

• Euratom

Koszt całkowity

€ 6 729 994,19

Wkład UE

€ 3 795 800,50

Koordynowany przez

COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
France

CORDIS oferuje możliwość skorzystania z odnośników do publicznie dostępnych publikacji i rezultatów projektów realizowanych w ramach programów ramowych HORYZONT.

Odnośniki do rezultatów i publikacji związanych z poszczególnymi projektami 7PR, a także odnośniki do niektórych konkretnych kategorii wyników, takich jak zbiory danych i oprogramowanie, są dynamicznie pobierane z systemu OpenAIRE .

Rezultaty

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

Publikacje

Peer reviewed articles (10)

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

Autorzy: M. Di Gennaro, A. Magni, M. Guarnieri, D. Pizzocri, L. Luzzi, C. Guéneau, P. Van Uffelen
Opublikowane w: Progress in Nuclear Energy, Numer 185, 2025, Strona(/y) 105698, ISSN 0149-1970
Wydawca: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105698

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

Autorzy: 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
Opublikowane w: Nuclear Engineering and Design, Numer 435, 2025, Strona(/y) 113960, ISSN 0029-5493
Wydawca: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.113960

ALFRED-burner: Core design, safety and performance

Autorzy: D. Jaramillo-Sierra, G. Grasso, E. Dorval, A. Magni, A. Cammi, A. Del Nevo
Opublikowane w: Nuclear Engineering and Design, Numer 432, 2025, Strona(/y) 113826, ISSN 0029-5493
Wydawca: 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

Autorzy: M.-M. Desagulier, J. Martinez, P.M. Martin, F. Lebreton, M.O.J.Y. Hunault, C. Guéneau, N. Clavier
Opublikowane w: Journal of the European Ceramic Society, Numer 45, 2025, Strona(/y) 117623, ISSN 0955-2219
Wydawca: Elsevier BV
DOI: 10.1016/j.jeurceramsoc.2025.117623

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

Autorzy: G. Porto, J. Bouchet, D. Bathellier, J. Bodin, M. Canducci, J. Tranchida, P. Fossati, P. Martin, E. Bourasseau
Opublikowane w: Journal of Nuclear Materials, Numer 598, 2025, Strona(/y) 155163, ISSN 0022-3115
Wydawca: Elsevier BV
DOI: 10.1016/j.jnucmat.2024.155163

Off-centering effects on MOX fuel behavior

Autorzy: D. Jaramillo-Sierra, V. Blanc, T. Barani, A. Cammi, A. Del Nevo
Opublikowane w: Nuclear Engineering and Design, Numer 444, 2025, Strona(/y) 114372, ISSN 0029-5493
Wydawca: 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

Autorzy: S. van Til, A.V. Fedorov, F. Nindiyasari, F. Charpin-Jacobs, G. Uitslag, F. Pasti, E. D'Agata, N. Chauvin
Opublikowane w: Journal of Nuclear Materials, Numer 608, 2025, Strona(/y) 155707, ISSN 0022-3115
Wydawca: Elsevier BV
DOI: 10.1016/j.jnucmat.2025.155707

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

Autorzy: Edoardo Luciano Brunetto, Carlo Fiorina, Andreas Pautz, Sander van Til, Fitriana Nindiyasari, Alexander Fedorov, Alessandro Scolaro
Opublikowane w: Journal of Nuclear Materials, Numer 608, 2025, Strona(/y) 155717, ISSN 0022-3115
Wydawca: 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

Autorzy: Martin Giraud, Nathalie Reynier-Tronche, Emilie Buravand
Opublikowane w: Journal of Nuclear Materials, 2023, ISSN 0022-3115
Wydawca: 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

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