Partitioning And Transmuter Research Initiative in a Collaborative Innovation Action

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

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

Publikacje

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

Autorzy: 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)
Opublikowane w: 16IEMPT Summary Report, Numer Nuclear Science NEA/NSC/R(2024)2, 2025
Wydawca: 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

Autorzy: 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)
Opublikowane w: 16IEMPT Summary Report, Numer Nuclear Science NEA/NSC/R(2024)2, 2025
Wydawca: OECD Publishing

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

Autorzy: P. Schuurmans, SCK CEN
Opublikowane w: 16IEMPT Summary Report, Numer Nuclear Science NEA/NSC/R(2024)2, 2025
Wydawca: OECD Publishing

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

Autorzy: M. Di Gennaro, A. Magni, M. Mastrogiovanni, D. Pizzocri, L. Luzzi (POLIMI)
Opublikowane w: 16IEMPT Summary Report, Numer Nuclear Science NEA/NSC/R(2024)2, 2025
Wydawca: OECD Publishing

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

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

Autorzy: Baptiste Labonne, Simon Orlat, Marjorie Bertolus
Opublikowane w: Journal of Nuclear Materials, Numer 579, 2025, Strona(/y) 154390, ISSN 0022-3115
Wydawca: 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

Autorzy: Fynn S. Sauerwein, Thomas Sittel, Andreas Geist, Petra J. Panak, Andreas Wilden, Giuseppe Modolo
Opublikowane w: EPJ Web of Conferences, Numer 317, 2025, Strona(/y) 01012, ISSN 2100-014X
Wydawca: 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

Autorzy: Weßling, P.; Maag, M.; Baruth, G.; Sittel, T.; Sauerwein, F. S.; Wilden, A.; Modolo, G.; Geist, A.; Panak, P. J.
Opublikowane w: Inorganic Chemistry, 2022, Strona(/y) 17719−17729, ISSN 0020-1669
Wydawca: American Chemical Society
DOI: 10.1021/acs.inorgchem.2c0287

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

Autorzy: Mathur A., Roelofs F., Fiore M., Koloszar L.
Opublikowane w: Nuclear Engineering & Design, Numer vol. 406, 112241, 2023, ISSN 0029-5493
Wydawca: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112241

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

Autorzy: M. Di Gennaro, A. Magni, M. Mastrogiovanni, L. Luzzi, D. Pizzocri
Opublikowane w: Nuclear Engineering and Design, Numer 428, 2024, Strona(/y) 113536, ISSN 0029-5493
Wydawca: 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

Autorzy: Pablo Vacas-Arquero, Iván Sánchez-García, Hitos Galán
Opublikowane w: Nuclear Engineering and Technology, Numer 58, 2026, Strona(/y) 104013, ISSN 1738-5733
Wydawca: Korean Nuclear Society
DOI: 10.1016/j.net.2025.104013

Autorzy: 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
Opublikowane w: Radiochimica Acta, Numer Volume 10/ 12 issues a year, 2022, Strona(/y) 515-525, ISSN 2193-3405
Wydawca: De Gruyter
DOI: 10.1515/ract-2022-0014

Experiments and CFD for Wire-Wrapped Fuel Assembly Blockages

Autorzy: Ferry Roelofs, Akshat Mathur, Heleen Uitslag-Doolaard, Markus Daubner, Karsten Litfin, Julio Pacio, Yassin Hassan
Opublikowane w: Nuclear Technology, 2025, Strona(/y) 1-15, ISSN 0029-5450
Wydawca: American Nuclear Society
DOI: 10.1080/00295450.2025.2516179

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

Autorzy: S. van Til, P.R. Hania, A.V. Fedorov, E. D'Agata, D. Freis, S. Bejaoui, F. Delage, A. Gallais-During
Opublikowane w: Journal of Nuclear Materials, Numer 587, 2025, Strona(/y) 154699, ISSN 0022-3115
Wydawca: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154699

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

Autorzy: Pietro Stefanini, Francesco Galleni, Ivan Di Piazza, Andrea Pucciarelli
Opublikowane w: Nuclear Technology, Numer 210, 2024, Strona(/y) 629-643, ISSN 0029-5450
Wydawca: 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

Autorzy: Pablo Vacas-Arquero, Iván Sánchez-García, Hitos Galán
Opublikowane w: Progress in Nuclear Energy, Numer 183, 2025, Strona(/y) 105677, ISSN 0149-1970
Wydawca: Elsevier BV
DOI: 10.1016/j.pnucene.2025.105677

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

Autorzy: 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
Opublikowane w: Energies; Volume 14; Numer 16; Pages: 5157, Numer 14, 2021, ISSN 1996-1073
Wydawca: Multidisciplinary Digital Publishing Institute (MDPI)
DOI: 10.3390/en14165157

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

Autorzy: R. Giorgi, A. Cechet, L. Cognini, A. Magni, D. Pizzocri, G. Zullo, A. Schubert, P. Van Uffelen, L. Luzzi
Opublikowane w: Nuclear Engineering and Technology, Numer Volume 54, 2022, Strona(/y) 2367-2375, ISSN 1738-5733
Wydawca: Korean Nuclear Society
DOI: 10.1016/j.net.2022.01.012

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

Autorzy: Pietro Stefanini, Andrea Pucciarelli, Ivan Di Piazza, Daniele Martelli, Nicola Forgione
Opublikowane w: Annals of Nuclear Energy, Numer 213, 2025, Strona(/y) 111102, ISSN 0306-4549
Wydawca: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2024.111102

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

Autorzy: Vincent Moreau
Opublikowane w: Open Research Europe, 2023, ISSN 2046-1402
Wydawca: F1000 Research Ltd.
DOI: 10.12688/openreseurope.15367.1

Speciation and Ammonia-Induced Precipitation of Neptunium and Uranium Ions

Autorzy: Leinders, Gregory; Acevedo, Beatriz; Jutier, Frédéric; Colak, Gamze; Verwerft, Marc
Opublikowane w: Crossref, Numer 4, 2023, ISSN 0020-1669
Wydawca: 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

Autorzy: L. Luzzi, A. Magni, S. Billiet, M. Di Gennaro, G. Leinders, L.G. Mariano, D. Pizzocri, M. Zanetti, G. Zullo
Opublikowane w: Nuclear Engineering and Design, Numer 420, 2024, Strona(/y) 113048, ISSN 0029-5493
Wydawca: 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

Autorzy: Giovanni Nicodemo, Christine Guéneau, Paul C.M. Fossati, Giovanni Zullo, Davide Pizzocri, Lelio Luzzi
Opublikowane w: Computational Materials Science, Numer 269, 2026, Strona(/y) 114607, ISSN 0927-0256
Wydawca: Elsevier BV
DOI: 10.1016/j.commatsci.2026.114607

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

Autorzy: Manuela Profir, Vincent Moreau
Opublikowane w: Nuclear Technology, Numer 210, 2024, Strona(/y) 565-578, ISSN 0029-5450
Wydawca: 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

Autorzy: M. Di Gennaro, A. Magni, A. Trombetta, D. Pizzocri, S. Lorenzi, L. Luzzi
Opublikowane w: Nuclear Engineering and Design, Numer 436, 2025, Strona(/y) 113944, ISSN 0029-5493
Wydawca: 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

Autorzy: M. Romano, D. Pizzocri, L. Luzzi
Opublikowane w: Nuclear Engineering and Design, Numer Volume 54, Numer 5, 2021, Strona(/y) 1929-1934, ISSN 1738-5733
Wydawca: 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

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

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

Autorzy: 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.
Opublikowane w: Nuclear Engineering & Design, Numer vol. 412, 112473, 2023, ISSN 0029-5493
Wydawca: Elsevier BV
DOI: 10.1016/j.nucengdes.2023.112473

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

Autorzy: 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.
Opublikowane w: ATALANTE2024 Proceedings, 2025
Wydawca: EPJ Web of Conferences

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

Autorzy: Habiyaremye V., Mathur A., Roelofs F.
Opublikowane w: NURETH20, 2023
Wydawca: ANS

Fast Reactor Thermal Hydraulics in the Dutch PIONEER Program

Autorzy: 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.
Opublikowane w: IAEA Technical Meeting on State-of-the-Art Thermal Hydraulics of Fast Reactors, 2022
Wydawca: IAEA

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

Autorzy: Habiyaremye V., Mathur A., Roelofs F. (NRG PALLAS)
Opublikowane w: ATH2024 Proceedings, 2025, Strona(/y) 726-729
Wydawca: American Nuclear Society (ANS)

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

Autorzy: Pietro Stefanini, Andrea Pucciarelli, Nicola Forgione, Ivan Di Piazza
Opublikowane w: ICONE31 Proceedings, 2024, ISBN 978-0-7918-8821-6
Wydawca: The American Society of Mechanical Engineers (ASME)

Analyzing the Effect of Deformed Pins in LMFR Rod Bundles

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

Quantitative Availability Modelling for the MYRRHA ADS

Autorzy: Lukas Felsberger, Andrea Apollonio, Jan Uythoven (CERN), Ulrich Dorda, Dirk Vandeplassche, Jarno Van de Walle (SCK CEN)
Opublikowane w: IPAC'23 - Proceedings, Numer THPM105, 2023, Strona(/y) 5114-5117, ISBN 978-3-95450-231-8
Wydawca: JACoW Publishing

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

Autorzy: R. Giorgi, A. Cechet, L. Cognini, A. Magni, D. Pizzocri, L. Luzzi, A. Schubert, P. Van Uffelen
Opublikowane w: ProceedingsTop Fuel 2021, 2021, ISBN 978-92-95064-35-5
Wydawca: ANS

Experiments and CFD for Wire-wrapped Fuel Assembly Blockages

Autorzy: Ferry Roelofs, Akshat Mathur, and Heleen Uitslag-Doolaard (NRG), Markus Daubner, Karsten Litfin (KIT), Julio Pacio (SCK CEN)
Opublikowane w: NUTHOS-14 Proceedings, 2024, Strona(/y) 1960-1971
Wydawca: American Nuclear Society (ANS)

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

Autorzy: Mathur A., Roelofs F., Fiore M., Koloszar L.
Opublikowane w: IAEA Technical Meeting on State-of-the-Art Thermal Hydraulics of Fast Reactors, 2022
Wydawca: 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

Autorzy: Oder, Jure; Coëpeau, Alexis; Koloszar, Lilla; Laboureur, Delphine; Keijers, Steven
Opublikowane w: NURETH20, Numer 4, 2023
Wydawca: ANS
DOI: 10.13182/NURETH20-40356

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

Autorzy: Victor Habiyaremye,Akshat Mathur, and Ferry Roelofs (NRG PALLAS)
Opublikowane w: ATH2024 Proceedings, 2025, Strona(/y) 726-729, ISBN 9798331311148
Wydawca: American Nuclear Society

LIQUID METAL THERMAL HYDRAULIC ACTIVITIES IN EUROPEAN COLLABORATIVE PROJECTS

Autorzy: F. Roelofs (NRG), M. Tarantino, G. Grasso (ENEA), K. Van Tichelen P. Schuurmans (SCK CEN)
Opublikowane w: Proceedings NURETH19, Numer Log nr 34010, 2022
Wydawca: ANS

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

Autorzy: M. Profir, V. Moreau (CRS4), D. Martelli, I. Di Piazza, P. Lorusso, M. Tarantino (ENEA)
Opublikowane w: Proceedings NURETH19, Numer Log nr 35033, 2022
Wydawca: ANS

Advances in Thermal Hydraulics in the Dutch PIONEER Program

Autorzy: 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.
Opublikowane w: ATH2024 Proceedings, 2025, Strona(/y) 83-92
Wydawca: American Nuclear Society (ANS)

Simulating Wire-wrapped Fuel Assembly Blockages in CFD

Autorzy: Roelofs F., Mathur A., Uitslag-Doolaard H.
Opublikowane w: ANS Annual Meeting, 2023
Wydawca: ANS

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

Autorzy: Pangukir F., Visser D., Roelofs F., Pacio J., Van Tichelen K.
Opublikowane w: NURETH20, 2023
Wydawca: ANS

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

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

Dutch Thermal Hydraulic Design and Safety Support for LMFRs

Autorzy: Roelofs F., Visser D., Zwijsen K., Uitslag-Doolaard H.
Opublikowane w: Fast Reactor Conference 2022, 2022
Wydawca: IAEA

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

Autorzy: Lukas Felsberger, Andrea Apollonio, Thomas Cartier-Michaud, Eric Montesinos, Jan Uythoven
Opublikowane w: 12th International Particle Accelerator Conference proceedings, 2021, Strona(/y) 2308-2311, ISBN 978-3-95450-214-1
Wydawca: JACoW

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

Autorzy: Stefanini Pietro, Nicola Forgione; Andrea Pucciarelli, University of Pisa
Opublikowane w: NURETH20 Proceedings, 2023, ISBN 979-8-3313-0129-3
Wydawca: American Nuclear Society

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

Autorzy: A. Magni (POLIMI)
Opublikowane w: 2022
Wydawca: POLIMI

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

Autorzy: Giana Baruth (UHEI)
Opublikowane w: 2025
Wydawca: Heidelberg University

Evaporation of Polonium and Tellurium from Lead-Bismuth Eutectic Coolants

Autorzy: Ivan Zivadinovic
Opublikowane w: 2025
Wydawca: 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

Autorzy: Giovanni Zullo (Politecnico di Milano,Department of Energy, Doctoral Program in Energy and Nuclear Science and Technology)
Opublikowane w: 2024
Wydawca: Politecnico di Milano

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