Partitioning And Transmuter Research Initiative in a Collaborative Innovation Action

CORDIS proporciona enlaces a los documentos públicos y las publicaciones de los proyectos de los programas marco HORIZONTE.

Los enlaces a los documentos y las publicaciones de los proyectos del Séptimo Programa Marco, así como los enlaces a algunos tipos de resultados específicos, como conjuntos de datos y «software», se obtienen dinámicamente de OpenAIRE .

Resultado final

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

Publicaciones

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

Autores: 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)
Publicado en: 16IEMPT Summary Report, Edición Nuclear Science NEA/NSC/R(2024)2, 2025
Editor: 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

Autores: 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)
Publicado en: 16IEMPT Summary Report, Edición Nuclear Science NEA/NSC/R(2024)2, 2025
Editor: OECD Publishing

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

Autores: P. Schuurmans, SCK CEN
Publicado en: 16IEMPT Summary Report, Edición Nuclear Science NEA/NSC/R(2024)2, 2025
Editor: OECD Publishing

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

Autores: M. Di Gennaro, A. Magni, M. Mastrogiovanni, D. Pizzocri, L. Luzzi (POLIMI)
Publicado en: 16IEMPT Summary Report, Edición Nuclear Science NEA/NSC/R(2024)2, 2025
Editor: OECD Publishing

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

Autores: I. Sánchez-García, P. Vacas-Arquero, L. J. Bonales, A. Núñez,1 L. Serrano, R. J. M. Egberink, W. Verboom and H. Galán
Publicado en: 16IEMPT Summary Report, Edición Nuclear Science NEA/NSC/R(2024)2, 2025
Editor: 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%

Autores: Baptiste Labonne, Simon Orlat, Marjorie Bertolus
Publicado en: Journal of Nuclear Materials, Edición 579, 2025, Página(s) 154390, ISSN 0022-3115
Editor: 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

Autores: Fynn S. Sauerwein, Thomas Sittel, Andreas Geist, Petra J. Panak, Andreas Wilden, Giuseppe Modolo
Publicado en: EPJ Web of Conferences, Edición 317, 2025, Página(s) 01012, ISSN 2100-014X
Editor: 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

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

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

Autores: Mathur A., Roelofs F., Fiore M., Koloszar L.
Publicado en: Nuclear Engineering & Design, Edición vol. 406, 112241, 2023, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112241

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

Autores: M. Di Gennaro, A. Magni, M. Mastrogiovanni, L. Luzzi, D. Pizzocri
Publicado en: Nuclear Engineering and Design, Edición 428, 2024, Página(s) 113536, ISSN 0029-5493
Editor: 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

Autores: Pablo Vacas-Arquero, Iván Sánchez-García, Hitos Galán
Publicado en: Nuclear Engineering and Technology, Edición 58, 2026, Página(s) 104013, ISSN 1738-5733
Editor: Korean Nuclear Society
DOI: 10.1016/j.net.2025.104013

Autores: 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
Publicado en: Radiochimica Acta, Edición Volume 10/ 12 issues a year, 2022, Página(s) 515-525, ISSN 2193-3405
Editor: De Gruyter
DOI: 10.1515/ract-2022-0014

Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages

Autores: Ferry Roelofs, Akshat Mathur, Heleen Uitslag-Doolaard, Markus Daubner, Karsten Litfin, Julio Pacio, Yassin Hassan
Publicado en: Nuclear Technology, 2025, Página(s) 1-15, ISSN 0029-5450
Editor: American Nuclear Society
DOI: 10.1080/00295450.2025.2516179

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

Autores: S. van Til, P.R. Hania, A.V. Fedorov, E. D'Agata, D. Freis, S. Bejaoui, F. Delage, A. Gallais-During
Publicado en: Journal of Nuclear Materials, Edición 587, 2025, Página(s) 154699, ISSN 0022-3115
Editor: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154699

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

Autores: Pietro Stefanini, Francesco Galleni, Ivan Di Piazza, Andrea Pucciarelli
Publicado en: Nuclear Technology, Edición 210, 2024, Página(s) 629-643, ISSN 0029-5450
Editor: 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

Autores: Pablo Vacas-Arquero, Iván Sánchez-García, Hitos Galán
Publicado en: Progress in Nuclear Energy, Edición 183, 2025, Página(s) 105677, ISSN 0149-1970
Editor: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105677

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

Autores: 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
Publicado en: Energies; Volume 14; Edición 16; Pages: 5157, Edición 14, 2021, ISSN 1996-1073
Editor: Multidisciplinary Digital Publishing Institute (MDPI)
DOI: 10.3390/en14165157

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

Autores: R. Giorgi, A. Cechet, L. Cognini, A. Magni, D. Pizzocri, G. Zullo, A. Schubert, P. Van Uffelen, L. Luzzi
Publicado en: Nuclear Engineering and Technology, Edición Volume 54, 2022, Página(s) 2367-2375, ISSN 1738-5733
Editor: Korean Nuclear Society
DOI: 10.1016/j.net.2022.01.012

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

Autores: Pietro Stefanini, Andrea Pucciarelli, Ivan Di Piazza, Daniele Martelli, Nicola Forgione
Publicado en: Annals of Nuclear Energy, Edición 213, 2025, Página(s) 111102, ISSN 0306-4549
Editor: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2024.111102

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

Autores: Vincent Moreau
Publicado en: Open Research Europe, 2023, ISSN 2046-1402
Editor: F1000 Research Ltd.
DOI: 10.12688/openreseurope.15367.1

Speciation and Ammonia-Induced Precipitation of Neptunium and Uranium Ions

Autores: Leinders, Gregory; Acevedo, Beatriz; Jutier, Frédéric; Colak, Gamze; Verwerft, Marc
Publicado en: Crossref, Edición 4, 2023, ISSN 0020-1669
Editor: 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

Autores: L. Luzzi, A. Magni, S. Billiet, M. Di Gennaro, G. Leinders, L.G. Mariano, D. Pizzocri, M. Zanetti, G. Zullo
Publicado en: Nuclear Engineering and Design, Edición 420, 2024, Página(s) 113048, ISSN 0029-5493
Editor: 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

Autores: Giovanni Nicodemo, Christine Guéneau, Paul C.M. Fossati, Giovanni Zullo, Davide Pizzocri, Lelio Luzzi
Publicado en: Computational Materials Science, Edición 269, 2026, Página(s) 114607, ISSN 0927-0256
Editor: Elsevier BV
DOI: 10.1016/j.commatsci.2026.114607

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

Autores: Manuela Profir, Vincent Moreau
Publicado en: Nuclear Technology, Edición 210, 2024, Página(s) 565-578, ISSN 0029-5450
Editor: 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

Autores: M. Di Gennaro, A. Magni, A. Trombetta, D. Pizzocri, S. Lorenzi, L. Luzzi
Publicado en: Nuclear Engineering and Design, Edición 436, 2025, Página(s) 113944, ISSN 0029-5493
Editor: 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

Autores: M. Romano, D. Pizzocri, L. Luzzi
Publicado en: Nuclear Engineering and Design, Edición Volume 54, Edición 5, 2021, Página(s) 1929-1934, ISSN 1738-5733
Editor: 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

Autores: M. Di Gennaro, A. Magni, M. Guarnieri, D. Pizzocri, L. Luzzi, C. Guéneau, P. Van Uffelen
Publicado en: Progress in Nuclear Energy, Edición 185, 2025, Página(s) 105698, ISSN 0149-1970
Editor: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105698

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

Autores: 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.
Publicado en: Nuclear Engineering & Design, Edición vol. 412, 112473, 2023, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112473

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

Autores: 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.
Publicado en: ATALANTE2024 Proceedings, 2025
Editor: EPJ Web of Conferences

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

Autores: Habiyaremye V., Mathur A., Roelofs F.
Publicado en: NURETH20, 2023
Editor: ANS

Fast Reactor Thermal Hydraulics in the Dutch PIONEER Program

Autores: 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.
Publicado en: IAEA Technical Meeting on State-of-the-Art Thermal Hydraulics of Fast Reactors, 2022
Editor: IAEA

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

Autores: Habiyaremye V., Mathur A., Roelofs F. (NRG PALLAS)
Publicado en: ATH2024 Proceedings, 2025, Página(s) 726-729
Editor: American Nuclear Society (ANS)

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

Autores: Pietro Stefanini, Andrea Pucciarelli, Nicola Forgione, Ivan Di Piazza
Publicado en: ICONE31 Proceedings, 2024, ISBN 978-0-7918-8821-6
Editor: The American Society of Mechanical Engineers (ASME)

Analyzing the Effect of Deformed Pins in LMFR Rod Bundles

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

Quantitative Availability Modelling for the MYRRHA ADS

Autores: Lukas Felsberger, Andrea Apollonio, Jan Uythoven (CERN), Ulrich Dorda, Dirk Vandeplassche, Jarno Van de Walle (SCK CEN)
Publicado en: IPAC'23 - Proceedings, Edición THPM105, 2023, Página(s) 5114-5117, ISBN 978-3-95450-231-8
Editor: JACoW Publishing

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

Autores: R. Giorgi, A. Cechet, L. Cognini, A. Magni, D. Pizzocri, L. Luzzi, A. Schubert, P. Van Uffelen
Publicado en: ProceedingsTop Fuel 2021, 2021, ISBN 978-92-95064-35-5
Editor: ANS

Experiments and CFD for Wire-wrapped Fuel Assembly Blockages

Autores: Ferry Roelofs, Akshat Mathur, and Heleen Uitslag-Doolaard (NRG), Markus Daubner, Karsten Litfin (KIT), Julio Pacio (SCK CEN)
Publicado en: NUTHOS-14 Proceedings, 2024, Página(s) 1960-1971
Editor: American Nuclear Society (ANS)

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

Autores: Mathur A., Roelofs F., Fiore M., Koloszar L.
Publicado en: IAEA Technical Meeting on State-of-the-Art Thermal Hydraulics of Fast Reactors, 2022
Editor: 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

Autores: Oder, Jure; Coëpeau, Alexis; Koloszar, Lilla; Laboureur, Delphine; Keijers, Steven
Publicado en: NURETH20, Edición 4, 2023
Editor: ANS
DOI: 10.13182/NURETH20-40356

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

Autores: Victor Habiyaremye,Akshat Mathur, and Ferry Roelofs (NRG PALLAS)
Publicado en: ATH2024 Proceedings, 2025, Página(s) 726-729, ISBN 9798331311148
Editor: American Nuclear Society

LIQUID METAL THERMAL HYDRAULIC ACTIVITIES IN EUROPEAN COLLABORATIVE PROJECTS

Autores: F. Roelofs (NRG), M. Tarantino, G. Grasso (ENEA), K. Van Tichelen P. Schuurmans (SCK CEN)
Publicado en: Proceedings NURETH19, Edición Log nr 34010, 2022
Editor: ANS

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

Autores: M. Profir, V. Moreau (CRS4), D. Martelli, I. Di Piazza, P. Lorusso, M. Tarantino (ENEA)
Publicado en: Proceedings NURETH19, Edición Log nr 35033, 2022
Editor: ANS

Advances in Thermal Hydraulics in the Dutch PIONEER Program

Autores: 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.
Publicado en: ATH2024 Proceedings, 2025, Página(s) 83-92
Editor: American Nuclear Society (ANS)

Simulating Wire-wrapped Fuel Assembly Blockages in CFD

Autores: Roelofs F., Mathur A., Uitslag-Doolaard H.
Publicado en: ANS Annual Meeting, 2023
Editor: ANS

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

Autores: Pangukir F., Visser D., Roelofs F., Pacio J., Van Tichelen K.
Publicado en: NURETH20, 2023
Editor: ANS

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

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

Dutch Thermal Hydraulic Design and Safety Support for LMFRs

Autores: Roelofs F., Visser D., Zwijsen K., Uitslag-Doolaard H.
Publicado en: Fast Reactor Conference 2022, 2022
Editor: IAEA

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

Autores: Lukas Felsberger, Andrea Apollonio, Thomas Cartier-Michaud, Eric Montesinos, Jan Uythoven
Publicado en: 12th International Particle Accelerator Conference proceedings, 2021, Página(s) 2308-2311, ISBN 978-3-95450-214-1
Editor: JACoW

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

Autores: Stefanini Pietro, Nicola Forgione; Andrea Pucciarelli, University of Pisa
Publicado en: NURETH20 Proceedings, 2023, ISBN 979-8-3313-0129-3
Editor: American Nuclear Society

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

Autores: A. Magni (POLIMI)
Publicado en: 2022
Editor: POLIMI

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

Autores: Giana Baruth (UHEI)
Publicado en: 2025
Editor: Heidelberg University

Evaporation of Polonium and Tellurium from Lead-Bismuth Eutectic Coolants

Autores: Ivan Zivadinovic
Publicado en: 2025
Editor: 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

Autores: Giovanni Zullo (Politecnico di Milano,Department of Energy, Doctoral Program in Energy and Nuclear Science and Technology)
Publicado en: 2024
Editor: Politecnico di Milano

Buscando datos de OpenAIRE...

Resultado final

Publicaciones

Compartir esta página Compartir esta página en las redes sociales

Descargar Descargar el contenido de la página