Partitioning And Transmuter Research Initiative in a Collaborative Innovation Action

CORDIS fournit des liens vers les livrables publics et les publications des projets HORIZON.

Les liens vers les livrables et les publications des projets du 7e PC, ainsi que les liens vers certains types de résultats spécifiques tels que les jeux de données et les logiciels, sont récupérés dynamiquement sur OpenAIRE .

Livrables

Small punch, tensile tests and ring tests results
Simulation and optimization of performance during normal operating conditions of a MA-bearing fuel pin; comparison with ADS-MYRRHA targets
SAS and DES simulations of the Backwards Facing Step

Simulations of the Backwards Facing Step

Impact and detection of a failure of the beam window in ADS with lead bismuth eutectic
Fuel coolant interaction tests report
Description of new meso-scale models and their implementation in fuel performance codes
Pre- and post-test simulation of deformed fuel assembly experiments
Report on the natural circulation CFD simulations in CIRCE
Description of new correlations/databases for fuel performance codes to be applied to Am-bearing fuels
Experimental assessment of fuel assembly corrosion and blockage phenomena
Numerical simulations of coolant chemistry behaviour in the MYRRHA reactor system
Experimental studies of polonium release from LBE
Experimental results on wire-spaced fuel assembly with porous blockage
Public Report
Overview booklet
Report of experiments on the preparation of Os, Ru and Re doped LBE samples for evaporation studies
Microstructural and chemical evolution
Towards multi-physics description of fuel behaviour for accidental conditions
Results of the fuel performance code benchmark/assessment
Final report on thermydynamic models of U-Pu-Am-Np-O systems
Experimental and numerical investigation of blockage in a transparent wire wrapped fuel bundle

Experimental and numerical investigation of blockage in a transparent wire wrapped fuel bundle.Deliverable will be written by International partner TAMUS.

Simulations of porous blockage experiments and self-heating porous blockages
Evaluation of out-of-pile experimental capabilities for code validation for off-normal conditions
Proceedings of the international workshop
Report on the natural circulation experiments in CIRCE
Measurements and atomic scale calculations in U-Pu-Am-Np-O systems
Project presentation
Experimental results on deformed fuel assembly geometries
Educational events
Design and safety analysis of a transient irradiation test for MA fuel in BR-2
Design and fabrication of the 7-pin heated bundle and integration into 15-15Ti cladding tubes

Design and fabrication of the 7pin heated bundle and integration into 1515Ti cladding tubes

Project quality plan including measure of success
KEMS study of the thermodynamic properties of tellurium in LBE
Accelerator reliability studies with emphasis on the fault tolerance capabilities
Design and safety analysis of ETNA - a facility to simulate transient scenario on MA fuel
Materials selection and conditions

Materials selection and conditions this deliverable will include a description of the material available for the project and the exposure conditions

Pre-test and post-test numerical analysis of coolant chemistry behaviour in the non-isothermal LBE loop MEXICO
T1 and Rh release from LBE
Report on the natural circulation STH and STH+CFD simulations in CIRCE
Transient simulation of the in-pile performance of a MA-bearing fuel pin
MARINE gas puncturing and swelling behaviour of (U, Am)02

MARINE gas puncturing and swelling behaviour of U Am02

Detailed Dissemination, Exploitation and Communication action plan
Internal pressure tests results
Experimental and quantum chemical characterization of volatile tellurium and polonium molecules
Report on the comparison of the explicit AHFM with available test cases and on the implementation of the implicit AHFM in OpenFOAM
Data Management and Quality Plan

Data Management Plan

Data Management Plan: needs to be updated in the course of the project whenever significant changes arise such as: new data; changes in consortium policies (e.g. new innovation potential, decision to file for a patent); changes in consortium composition and external factors (e.g. new consortium members joining or members leaving).

Project dissemination materials - webpage, poster, presentation, leaflet

Project dissemination materials – webpage, poster, presentation, leaflet

Publications

Advanced interpretation of the SPHERE irradiation experiment with neutronics and fuel performance codes

Auteurs: M. Lainet (CEA), L. Luzzi, A. Magni, D. Pizzocri, M. Di Gennaro (POLIMI) 2, P. Van Uffelen, A. Schubert, E. D’Agata (JRC), V. Romanello (CVR), A. Rineiski, M. Massone (KIT), S. Gianfelici (ENEA), S. van Til, F. Charpin, A. Fedorov (NRG)
Publié dans: 16IEMPT Summary Report, Numéro Nuclear Science NEA/NSC/R(2024)2, 2025
Éditeur: OECD Publishing

Selective actinide(III) separation using 2,6-bis[1-(propan-1-ol)-1,2,3-triazol-4-yl]pyridine (PyTri-Diol) in the innovative-SANEX process: laboratory scale counter current centrifugal contactor demonstration

Auteurs: Andreas Wilden, Dimitri Schneider, Zaina Paparigas, Maximilian Henkes, Fabian Kreft (FZJ), Andreas Geist (KIT), Eros Mossini, Elena Macerata, Mario Mariani (POLIMI), Maria Chiara Gullo, Alessandro Casnati (UNI PARMA), Giuseppe Modolo (FZJ)
Publié dans: 16IEMPT Summary Report, Numéro Nuclear Science NEA/NSC/R(2024)2, 2025
Éditeur: OECD Publishing

PATRICIA: Partitioning and Transmutation Research Initiative in a Collaborative Innovation Action

Auteurs: P. Schuurmans, SCK CEN
Publié dans: 16IEMPT Summary Report, Numéro Nuclear Science NEA/NSC/R(2024)2, 2025
Éditeur: OECD Publishing

OpenFOAM-informed TRANSURANUS simulation of the fuel pin behaviour in the MYRRHA reactor during BPJ transient scenario

Auteurs: M. Di Gennaro, A. Magni, M. Mastrogiovanni, D. Pizzocri, L. Luzzi (POLIMI)
Publié dans: 16IEMPT Summary Report, Numéro Nuclear Science NEA/NSC/R(2024)2, 2025
Éditeur: OECD Publishing

Effects of metal complexation on radiolytic stability of important minor actinide extractants for advanced nuclear fuel cycles

Auteurs: I. Sánchez-García, P. Vacas-Arquero, L. J. Bonales, A. Núñez,1 L. Serrano, R. J. M. Egberink, W. Verboom and H. Galán
Publié dans: 16IEMPT Summary Report, Numéro Nuclear Science NEA/NSC/R(2024)2, 2025
Éditeur: OECD Publishing

Development of an interatomic potential for mixed uranium-americium oxides and application to the determination of the structural and thermodynamic properties of (U,Am)O2 with americium contents below 50%

Auteurs: Baptiste Labonne, Simon Orlat, Marjorie Bertolus
Publié dans: Journal of Nuclear Materials, Numéro 579, 2025, Page(s) 154390, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154390

Selective Americium Separation: New Insights into the Complexation of Trivalent <i>f</i>-Elements with SO<sub>3</sub>-Ph-BTBP

Auteurs: Fynn S. Sauerwein, Thomas Sittel, Andreas Geist, Petra J. Panak, Andreas Wilden, Giuseppe Modolo
Publié dans: EPJ Web of Conferences, Numéro 317, 2025, Page(s) 01012, ISSN 2100-014X
Éditeur: EDP Sciences
DOI: 10.1051/epjconf/202531701012

Complexation and extraction studies of trivalent actinides and lanthanides with water-soluble and CHON-compatible ligands for the selective extraction of americium

Auteurs: Weßling, P.; Maag, M.; Baruth, G.; Sittel, T.; Sauerwein, F. S.; Wilden, A.; Modolo, G.; Geist, A.; Panak, P. J.
Publié dans: Inorganic Chemistry, 2022, Page(s) 17719−17729, ISSN 0020-1669
Éditeur: American Chemical Society
DOI: 10.1021/acs.inorgchem.2c0287

State-of-the-art turbulent heat flux modelling for low-Prandtl flows

Auteurs: Mathur A., Roelofs F., Fiore M., Koloszar L.
Publié dans: Nuclear Engineering & Design, Numéro vol. 406, 112241, 2023, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112241

A methodology for accelerated design of irradiation experiments: Demonstration via an OpenFOAM-informed TRANSURANUS simulation

Auteurs: M. Di Gennaro, A. Magni, M. Mastrogiovanni, L. Luzzi, D. Pizzocri
Publié dans: Nuclear Engineering and Design, Numéro 428, 2024, Page(s) 113536, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2024.113536

Evaluation of the stability of the full AmSel stripping system to recover americium from PUREX raffinate

Auteurs: Pablo Vacas-Arquero, Iván Sánchez-García, Hitos Galán
Publié dans: Nuclear Engineering and Technology, Numéro 58, 2026, Page(s) 104013, ISSN 1738-5733
Éditeur: Korean Nuclear Society
DOI: 10.1016/j.net.2025.104013

Auteurs: Andreas Wilden, Dimitri Schneider, Zaina Paparigas, Maximilian Henkes, Fabian Kreft, Andreas Geist, Eros Mossini, Elena Macerata, Mario Mariani, Maria Chiara Gullo, Alessandro Casnati, Giuseppe Modolo
Publié dans: Radiochimica Acta, Numéro Volume 10/ 12 issues a year, 2022, Page(s) 515-525, ISSN 2193-3405
Éditeur: De Gruyter
DOI: 10.1515/ract-2022-0014

Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages

Auteurs: Ferry Roelofs, Akshat Mathur, Heleen Uitslag-Doolaard, Markus Daubner, Karsten Litfin, Julio Pacio, Yassin Hassan
Publié dans: Nuclear Technology, 2025, Page(s) 1-15, ISSN 0029-5450
Éditeur: American Nuclear Society
DOI: 10.1080/00295450.2025.2516179

Irradiation performance and first examinations of Americium bearing blanket fuel from the MARINE irradiation experiment

Auteurs: S. van Til, P.R. Hania, A.V. Fedorov, E. D'Agata, D. Freis, S. Bejaoui, F. Delage, A. Gallais-During
Publié dans: Journal of Nuclear Materials, Numéro 587, 2025, Page(s) 154699, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154699

Liquid-Metal Thermal-Hydraulic Numerical Analyses in Support of the Upcoming CIRCE-THETIS Experimental Campaign

Auteurs: Pietro Stefanini, Francesco Galleni, Ivan Di Piazza, Andrea Pucciarelli
Publié dans: Nuclear Technology, Numéro 210, 2024, Page(s) 629-643, ISSN 0029-5450
Éditeur: American Nuclear Society
DOI: 10.1080/00295450.2023.2189892

Influence of the accumulation of TODGA degradation compounds in the separation of Americium from Curium by the AmSel process

Auteurs: Pablo Vacas-Arquero, Iván Sánchez-García, Hitos Galán
Publié dans: Progress in Nuclear Energy, Numéro 183, 2025, Page(s) 105677, ISSN 0149-1970
Éditeur: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105677

Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA

Auteurs: Mariano Tarantino; M. Angiolini; Serena Bassini; Sebastiano Cataldo; Chiara Ciantelli; C. Cristalli; Alessandro Del Nevo; Ivan Di Piazza; Dario Diamanti; Marica Eboli; A. Fiore; Giacomo Grasso; Francesco Lodi; P. Lorusso; R. Marinari; Daniele Martelli; Francesca Papa; Camillo Sartorio; Marco Utili; Alessandro Venturini
Publié dans: Energies; Volume 14; Numéro 16; Pages: 5157, Numéro 14, 2021, ISSN 1996-1073
Éditeur: Multidisciplinary Digital Publishing Institute (MDPI)
DOI: 10.3390/en14165157

Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX

Auteurs: R. Giorgi, A. Cechet, L. Cognini, A. Magni, D. Pizzocri, G. Zullo, A. Schubert, P. Van Uffelen, L. Luzzi
Publié dans: Nuclear Engineering and Technology, Numéro Volume 54, 2022, Page(s) 2367-2375, ISSN 1738-5733
Éditeur: Korean Nuclear Society
DOI: 10.1016/j.net.2022.01.012

Coupled STH/CFD calculations in support of the upcoming CIRCE-THETIS Experimental Campaign

Auteurs: Pietro Stefanini, Andrea Pucciarelli, Ivan Di Piazza, Daniele Martelli, Nicola Forgione
Publié dans: Annals of Nuclear Energy, Numéro 213, 2025, Page(s) 111102, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2024.111102

The SquAd derivation: A Square Additive approach to the turbulent Prandtl number

Auteurs: Vincent Moreau
Publié dans: Open Research Europe, 2023, ISSN 2046-1402
Éditeur: F1000 Research Ltd.
DOI: 10.12688/openreseurope.15367.1

Speciation and Ammonia-Induced Precipitation of Neptunium and Uranium Ions

Auteurs: Leinders, Gregory; Acevedo, Beatriz; Jutier, Frédéric; Colak, Gamze; Verwerft, Marc
Publié dans: Crossref, Numéro 4, 2023, ISSN 0020-1669
Éditeur: American Chemical Society
DOI: 10.1021/acs.inorgchem.3c00647

Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor

Auteurs: L. Luzzi, A. Magni, S. Billiet, M. Di Gennaro, G. Leinders, L.G. Mariano, D. Pizzocri, M. Zanetti, G. Zullo
Publié dans: Nuclear Engineering and Design, Numéro 420, 2024, Page(s) 113048, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2024.113048

Accelerating thermochemistry in MOX fuel modelling via neural-network surrogates of CALPHAD calculations: Integration into SCIANTIX

Auteurs: Giovanni Nicodemo, Christine Guéneau, Paul C.M. Fossati, Giovanni Zullo, Davide Pizzocri, Lelio Luzzi
Publié dans: Computational Materials Science, Numéro 269, 2026, Page(s) 114607, ISSN 0927-0256
Éditeur: Elsevier BV
DOI: 10.1016/j.commatsci.2026.114607

Steady-State and Transient Compliance of CIRCE-THETIS CFD Model

Auteurs: Manuela Profir, Vincent Moreau
Publié dans: Nuclear Technology, Numéro 210, 2024, Page(s) 565-578, ISSN 0029-5450
Éditeur: American Nuclear Society
DOI: 10.1080/00295450.2023.2175589

OpenFOAM-informed TRANSURANUS simulations for assessing the fuel pin performance in the MYRRHA in-pile test section

Auteurs: M. Di Gennaro, A. Magni, A. Trombetta, D. Pizzocri, S. Lorenzi, L. Luzzi
Publié dans: Nuclear Engineering and Design, Numéro 436, 2025, Page(s) 113944, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2025.113944

On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation

Auteurs: M. Romano, D. Pizzocri, L. Luzzi
Publié dans: Nuclear Engineering and Design, Numéro Volume 54, Numéro 5, 2021, Page(s) 1929-1934, ISSN 1738-5733
Éditeur: Korean Nuclear Society
DOI: 10.1016/j.net.2021.11.020

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

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

Fast Reactor Multi-Scale and Multi-Physics Modelling at NRG

Auteurs: Roelofs F., Uitslag-Doolaard H., Zwijsen K., Mathur A., Visser D., Frederix E., Dovizio D., Cervi E., Stempniewicz M., De Kock I., Breijder P., Komen E.
Publié dans: Nuclear Engineering & Design, Numéro vol. 412, 112473, 2023, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112473

Interinstitutional Study of the New EURO-GANEX Process Resistance by Gamma Irradiation Test Loops

Auteurs: Sanchez-Garcia, I. (Corresponding author); Hérès, X. ; Peterman, D. R. ; Galan, H. ; Costenoble, S. ; Broussard, S. ; Sinot, J. ; Grimes, T. S. ; Anderson, K. R. ; Jansone-Popva, S. ; Gullo, M. C. ; Casnati, A. ; Wilden, A.* ; Geist, A.
Publié dans: ATALANTE2024 Proceedings, 2025
Éditeur: EPJ Web of Conferences

Modeling of Forced Convection in low Prandtl Number Fluids Using a Novel Local Algebraic Heat Flux Model

Auteurs: Habiyaremye V., Mathur A., Roelofs F.
Publié dans: NURETH20, 2023
Éditeur: ANS

Fast Reactor Thermal Hydraulics in the Dutch PIONEER Program

Auteurs: Roelofs F., Uitslag-Doolaard H., Zwijsen K., Mathur A., Visser D., Frederix E., Dovizio D., Cervi E., Stempniewicz M., De Kock I., Breijder P., Komen E.
Publié dans: IAEA Technical Meeting on State-of-the-Art Thermal Hydraulics of Fast Reactors, 2022
Éditeur: IAEA

Modeling of Forced Convection in low Prandtl Number Fluids Using a Novel Local Algebraic Heat Flux Model

Auteurs: Habiyaremye V., Mathur A., Roelofs F. (NRG PALLAS)
Publié dans: ATH2024 Proceedings, 2025, Page(s) 726-729
Éditeur: American Nuclear Society (ANS)

Pre-Test Analysis of a PLOFA Scenario for CIRCE-THETIS Facility by Means of Coupled STH/CFD Calculations

Auteurs: Pietro Stefanini, Andrea Pucciarelli, Nicola Forgione, Ivan Di Piazza
Publié dans: ICONE31 Proceedings, 2024, ISBN 978-0-7918-8821-6
Éditeur: The American Society of Mechanical Engineers (ASME)

Analyzing the Effect of Deformed Pins in LMFR Rod Bundles

Auteurs: Ferry Roelofs, Akshat Mathur, and Heleen Uitslag-Doolaard (NRG), Markus Daubner, Karsten Litfin (KIT), Julio Pacio (SCK CEN)
Publié dans: NURETH21 Proceedings, 2025, ISBN 979-11-955566-6-3
Éditeur: American Nuclear Society (ANS)

Quantitative Availability Modelling for the MYRRHA ADS

Auteurs: Lukas Felsberger, Andrea Apollonio, Jan Uythoven (CERN), Ulrich Dorda, Dirk Vandeplassche, Jarno Van de Walle (SCK CEN)
Publié dans: IPAC'23 - Proceedings, Numéro THPM105, 2023, Page(s) 5114-5117, ISBN 978-3-95450-231-8
Éditeur: JACoW Publishing

A Physics-Based Description of Inter-Granular Helium Behaviour in SCIANTIX for Application in Fuel Performance Codes

Auteurs: R. Giorgi, A. Cechet, L. Cognini, A. Magni, D. Pizzocri, L. Luzzi, A. Schubert, P. Van Uffelen
Publié dans: ProceedingsTop Fuel 2021, 2021, ISBN 978-92-95064-35-5
Éditeur: ANS

Experiments and CFD for Wire-wrapped Fuel Assembly Blockages

Auteurs: Ferry Roelofs, Akshat Mathur, and Heleen Uitslag-Doolaard (NRG), Markus Daubner, Karsten Litfin (KIT), Julio Pacio (SCK CEN)
Publié dans: NUTHOS-14 Proceedings, 2024, Page(s) 1960-1971
Éditeur: American Nuclear Society (ANS)

State-of-the-Art Turbulent Heat Flux Modelling for Low-Prandtl Flows

Auteurs: Mathur A., Roelofs F., Fiore M., Koloszar L.
Publié dans: IAEA Technical Meeting on State-of-the-Art Thermal Hydraulics of Fast Reactors, 2022
Éditeur: IAEA

Analysis of the Anisotropic Term in the Implicit Algebraic Heat Flux Model in the Case of Low Prandtl Flow in Planar Impinging Jet Case

Auteurs: Oder, Jure; Coëpeau, Alexis; Koloszar, Lilla; Laboureur, Delphine; Keijers, Steven
Publié dans: NURETH20, Numéro 4, 2023
Éditeur: ANS
DOI: 10.13182/NURETH20-40356

Modeling of natural convection in low Prandtl number fluids using a novel local Algebraic Heat Flux Model

Auteurs: Victor Habiyaremye,Akshat Mathur, and Ferry Roelofs (NRG PALLAS)
Publié dans: ATH2024 Proceedings, 2025, Page(s) 726-729, ISBN 9798331311148
Éditeur: American Nuclear Society

LIQUID METAL THERMAL HYDRAULIC ACTIVITIES IN EUROPEAN COLLABORATIVE PROJECTS

Auteurs: F. Roelofs (NRG), M. Tarantino, G. Grasso (ENEA), K. Van Tichelen P. Schuurmans (SCK CEN)
Publié dans: Proceedings NURETH19, Numéro Log nr 34010, 2022
Éditeur: ANS

NUMERICAL MODELLING AND SIMULATION OF THE CIRCE FACILITY IN THE PATRICIA PROJECT

Auteurs: M. Profir, V. Moreau (CRS4), D. Martelli, I. Di Piazza, P. Lorusso, M. Tarantino (ENEA)
Publié dans: Proceedings NURETH19, Numéro Log nr 35033, 2022
Éditeur: ANS

Advances in Thermal Hydraulics in the Dutch PIONEER Program

Auteurs: Roelofs F., Verdonschot B.T.H., Pangukir F.S.L., Breijder P., Hussain M.M.M.D., Habiyaremye V., Frederix E., Mathur A., Zwijsen K., Uitslag-Doolaard H., Visser D.C., Stempniewicz M.M., Komen E.M.J.
Publié dans: ATH2024 Proceedings, 2025, Page(s) 83-92
Éditeur: American Nuclear Society (ANS)

Simulating Wire-wrapped Fuel Assembly Blockages in CFD

Auteurs: Roelofs F., Mathur A., Uitslag-Doolaard H.
Publié dans: ANS Annual Meeting, 2023
Éditeur: ANS

Comparison of System Thermal Hydraulic and CFD Analyses of E-SCAPE at forced circulation and under isothermal conditions

Auteurs: Pangukir F., Visser D., Roelofs F., Pacio J., Van Tichelen K.
Publié dans: NURETH20, 2023
Éditeur: ANS

PATRICIA: Partitioning And Transmuter Research Initiative in a Collaborative Innovation Action

Auteurs: P. Schuurmans (SCK CEN), S. Cornet (CEA), R. Delville (SCK CEN), L. Luzzi (POLIMI), F. Roelofs (NRG)
Publié dans: Proceedings 16IEMPT (Information Exchange Meeting on Actinide and Fission Product P&T), 2022
Éditeur: NEA

Dutch Thermal Hydraulic Design and Safety Support for LMFRs

Auteurs: Roelofs F., Visser D., Zwijsen K., Uitslag-Doolaard H.
Publié dans: Fast Reactor Conference 2022, 2022
Éditeur: IAEA

Availability Modelling of the Solid-State Power Amplifiers for the CERN SPS RF Upgrade

Auteurs: Lukas Felsberger, Andrea Apollonio, Thomas Cartier-Michaud, Eric Montesinos, Jan Uythoven
Publié dans: 12th International Particle Accelerator Conference proceedings, 2021, Page(s) 2308-2311, ISBN 978-3-95450-214-1
Éditeur: JACoW

CFD and STH Thermal-Hydraulic Analyses in support of the CIRCE-THETIS experimental campaign

Auteurs: Stefanini Pietro, Nicola Forgione; Andrea Pucciarelli, University of Pisa
Publié dans: NURETH20 Proceedings, 2023, ISBN 979-8-3313-0129-3
Éditeur: American Nuclear Society

Advancements in modelling the thermal-mechanical behaviour of MOX-fuelled pins and application to liquid-metal fast reactor conditions

Auteurs: A. Magni (POLIMI)
Publié dans: 2022
Éditeur: POLIMI

Extraction and spectroscopic speciation of trivalent actinides and lanthanides with tetradentate N-donor ligands

Auteurs: Giana Baruth (UHEI)
Publié dans: 2025
Éditeur: Heidelberg University

Evaporation of Polonium and Tellurium from Lead-Bismuth Eutectic Coolants

Auteurs: Ivan Zivadinovic
Publié dans: 2025
Éditeur: ETH Zürich
DOI: 10.3929/ethz-b-000736779

Development and assessment of an open-source code for gaseous and volatile fission product behaviour in light water reactor fuel

Auteurs: Giovanni Zullo (Politecnico di Milano,Department of Energy, Doctoral Program in Energy and Nuclear Science and Technology)
Publié dans: 2024
Éditeur: Politecnico di Milano

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