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thermal hydraulics Simulations and Experiments for the Safety Assessment of MEtal cooled reactors

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

TALL-3D setup for second series
Best Practise Guidelines for liquid metal flow simulation
Solidification model developement and validation

Solidification model developement and validation using Meliloo and TALL-3D data

BFS experiments

CIRCE-HERO blind simulations

CIRCE-HERO blind simulations (with contribution from NRG)

NACIE_UP blind simulations

NACIE_UP blind simulations (with contributions from UROM and GRS)

CIRCE-HERO test setup

CIRCE-HERO experimental setup and test matrix for PLOFA

CIRCE experiment: pre-test, data-set and analysis

CIRCE experiment: pre-test, data-set and analysis (with contributions from NRG and CRS4)

TALL-3D first series simulations: summary report

TALL-3D first series simulations: summary report (with contributions from GRS, TUM, and ENEA)

NACIE-UP data for PLOFA
TALL-3D solidification test setup

Description of the modified TALL-3D test facility and test matrix for solidification experiments

CFD analyses of BFPS

CFD post-test analysis of the BFPS experiments in NACIE-UP and application to an ALFRED fuel assembly

Solidification model performance
FIV model development in Fluent
SESAME Lecture Series publication
Coarse-mesh modelling

Development and validation of coarse-mesh models

Solification modelling: summary report
TALL-3D test setup

TALL-3D experimental test setup description for both test series

KALLA Inter-wrapper flow setup

KALLA experimental setup and test matrix for inter-wrapper flow

CIRCE experiment: CFD model validation

CIRCE experiment: CFD model validation (with contributions of NRG and ENEA)

AHFM in STAR-CCM+ and OpenFOAM

NACIE_UP simulation validation: summary report

NACIE_UP simulation validation: summary report (with contributions from UROM and GRS)

FLUENT solidification simulations

FLUENT simulations of Meliloo and TALL-3D facilities

DNS of mixing jets

BFS of DNS

Multi-scale model development and validation

Multi-scale model development and validation (with contribution from KIT)

TALL-3D: CFD models and validation

TALL-3D: CFD models and validation (with contribution from KTH)

Meliloo: pre-test simulations and measurements
CFD analyses for blocked and unblocked fuel assemblies

Validation of CFD analyses for an unblocked and blocked grid spacer fuel assembly and upscaling to an ALFRED fuel assembly

Training material for CFD code training

Training material for CFD code training (TransAT)

PHENIX dissymmetric test simulation validation: summary report

PHENIX dissymmetric test simulation validation: summary report (with contributions from KIT, NRG, IRSN, ENEA)

Infinite wire wrapped rod bundle

High fidelity numerical reference data for an infinite wire wrapped rod bundle

TALL-3D simulation validation: summary report

TALL-3D simulation validation: summary report (with contributions from GRS, TUM, and ENEA)

BFPS experiments

Experimental results of flow blockage experiments in the BFPS test section of the NACIE-UP facility

Nuclear Liquid Metal Thermal Hydraulics Textbook

Nuclear Liquid Metal Thermal Hydraulics Textbook (based on lecture series material, best practise guidelines, V&V, uncertainty qualification)

FIV model development in STAR-CCM+ or OpenFOAM

DNS of Mixed Convection

POD-ROM modelling

POD-ROM modelling of pool thermal hydraulics

V&V methodologies for liquid metal flow simulation
CIRCE-HERO PLOFA experiment
Pragmatic CFD approach for wire wrapped rod bundles

Validation of pragmatic CFD approaches for simulation of wire wrapped rod bundles

Wire wrap experiment

Results of matched index of refraction wire wrap rod bundle experiments

Coarse-grid CFD for the MYRRHA core

Coarse-grid CFD application to the full MYRRHA core

Entire core analysis in MATRA
Inter-wrapper flow CFD approach

Validation of a CFD approach to evaluate the influence of inter-wrapper flow

KALLA Inter-wrapper flow experiments

KALLA inter-wrapper flow experimental results

Experimental set-up BFPS

TMBF in TransAT

Code validation against TALL-3D solidification data
Reference data for rod bundle

High fidelity numerical reference data for flow and heat transfer in a rod bundle

TALL-3D setup for first series
PHENIX blind simulations

PHENIX blind simulations (with contribution from KIT, NRG, IRSN, ENEA)

Local heat transfer model
Preliminary design of MIR facility

Preliminary design of a matched index of refraction facility for wire wrapped rod bundles

Multi-scale complete core simulations

Multi-scale complete core simulations (with contribution from CEA)

Non-uniformly heated FPS experiments in the NACIE-UP facility
DNS and LES of liquid metal impinging jets

Meliloo setup

Description of the Meliloo test facility and test matrix

Preliminary design of FIV facility

Local turbulent Prandtl Number Model

CIRCE-HERO simulation validation: summary report

CIRCE-HERO simulation validation: summary report (with contribution from NRG)

NACIE-UP setup for PLOFA
TALL-3D STH / CFD simulations
FIV scaling laws water vs. liquid metal

Report on scaling laws for FIV considering water vs. liquid metal (with contribution from NRG)

Uncertainty quantification for liquid metal flow simulation

Publikacje

A fast algorithm for Direct Numerical Simulation of natural convection flows in arbitrarily-shaped periodic domains

Autorzy: D Angeli, E Stalio, M A Corticelli, G S Barozzi
Opublikowane w: Journal of Physics: Conference Series, Numer 655, 2015, Strona(/y) 012054, ISSN 1742-6588
Wydawca: Institute of Physics
DOI: 10.1088/1742-6596/655/1/012054

LDA measurements of coherent flow structures and cross-flow across the gap of a compound channel with two half-rods

Autorzy: F. Bertocchi, M. Rohde, J.L. Kloosterman
Opublikowane w: Nuclear Engineering and Design, Numer 326, 2018, Strona(/y) 17-30, ISSN 0029-5493
Wydawca: Elsevier BV
DOI: 10.1016/j.nucengdes.2017.10.023

Pre-test CFD simulations of the NACIE-UP BFPS test section

Autorzy: R. Marinari, I. Di Piazza, N. Forgione, F. Magugliani
Opublikowane w: Annals of Nuclear Energy, Numer 110, 2017, Strona(/y) 1060-1072, ISSN 0306-4549
Wydawca: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2017.08.046

The SESAME project: state of the art liquid metal thermal-hydraulics and beyond

Autorzy: F Roelofs, A Shams, A Batta, V Moreau, I Di Piazza, A Gerschenfeld, P Planquart, M Tarantino
Opublikowane w: atw: International Journal for Nuclear Power - Vol. 62 (2017) | Numer 8/9, August/September, 2017, Strona(/y) 531-537, ISSN 1431-5254
Wydawca: Verl.-Gruppe Handelsblatt

Experimental Activity for the Investigation of Mixing and Thermal Stratification Phenomena in the CIRCE Pool Facility

Autorzy: D. Martelli, M. Tarantino, I. Di Piazza
Opublikowane w: Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, 2016, Strona(/y) V004T10A027, ISBN 978-0-7918-5004-6
Wydawca: ASME
DOI: 10.1115/ICONE24-60920

Numerical simulation of mixing buoyant jets: preliminary studies

Autorzy: D Angeli, A Cimarelli, A Fregni, E Stalio, A Shams, F Roelofs
Opublikowane w: 2017
Wydawca: NURETH-17

CFD analyses of the internal blockage in the nacie-up fuel pin bundle simulator

Autorzy: Di Piazza, R. Marinari, N. Forgione
Opublikowane w: 2017
Wydawca: NURETH-17

Experimental study of the onset conditions for cross-flow through the gap between two half rods

Autorzy: F Bertocchi, M Rohde, J.L Kloosterman
Opublikowane w: 2017
Wydawca: NURETH-17

Numerical analysis of MYRRHA Inter-wrapper flow experiment at KALLA

Autorzy: A Batta, A Class
Opublikowane w: 2017
Wydawca: NURETH-17

Low Prandtl turbulent heat transfer in unconfined or wall-bounded configurations: DNS of a mixing layer and of an impinging jet

Autorzy: M Duponcheel, Y Bartosiewicz
Opublikowane w: 2017
Wydawca: NURETH-17

Experiment design to assess the inter-wrapper heat transfer in LMFR

Autorzy: H Doolaard, F Roelofs, J Pacio, A Batta
Opublikowane w: 2017
Wydawca: NURETH-17

Buoyancy-driven turbulent convection in a bundle of vertical heated cylinders

Autorzy: D Angeli , E Stalio
Opublikowane w: 2015
Wydawca: 15th EuropeanTurbulence Conference 2015 (ETC15)

Development of CFD models and pre-test calculations for thermal-hydraulics and freezing experiments on Lead coolant

Autorzy: M Iannone, I Dofek, T Melichar, W Borreani, G Lomonaco, V Moreau, M Profir
Opublikowane w: 2017
Wydawca: 26th International Conference Nuclear Energy for New Europe

Design and pre-evaluation of a backward facing step experiment with liquid metal coolant

Autorzy: W Jaeger, T Schaub Hahn, W Hering, I Otic, A Shams, J Oder, I Tiselj
Opublikowane w: 2017
Wydawca: NURETH-17

Direct numerical simulations of sodium flow over a backward facing step

Autorzy: J Oder, I Tiselj
Opublikowane w: 2017
Wydawca: NURETH-17

EUROPEAN OUTLOOK FOR LMFR THERMAL HYDRAULICS

Autorzy: Roelofs F., Shams A., Pacio J., Moreau V., Planquart P., Van Tichelen K., Di Piazza I., Tarantino M.
Opublikowane w: NURETH 16, 2015, Strona(/y) 7414-7425
Wydawca: NURETH

High-Fidelity Numerical Simulations of the Flow through an Infinite Wire-Wrapped Fuel Assembly.

Autorzy: Shams A., Roelofs F., Komen E.
Opublikowane w: NURETH 16, 2015, Strona(/y) 2817-2829
Wydawca: NURETH

Spectral Element Direct Numerical Simulation of Heat Transfer in Turbulent Channel Sodium Flow

Autorzy: Jure Oder, Jernej Urankar, Iztok Tiselj
Opublikowane w: NENE 2015, 2015
Wydawca: NENE

CFD pre-test analysis and design of the NACIE-UP BFPS fuel pin bundle simulator

Autorzy: R. Marinari, I. Di Piazza, M. Tarantino, F. Magugliani, A. Alemberti, W. Borreani, B.P. Ghionzoli
Opublikowane w: ICONE24 (2016), 2016, Strona(/y) 9
Wydawca: ASME

Vortex-induced vibrations by axial flow in a bundle of cylinders

Autorzy: Jeroen De Ridder, Katrien Van Tichelen, Joris Degroote, Jan Vierendeels
Opublikowane w: International Conference on Flow-Induced Vibration, Numer 11, 2016, Strona(/y) 8 pages
Wydawca: TNO

Blind simulations of NACIE-UP experimental tests by STH codes

Autorzy: Forgione, Nicola; Polidori, Massimiliano; Angelucci, Morena; Cervone, Antonio; Barone, Gianluca; Piazza, Ivan Di; Giannetti, Fabio; Hollands, Thorsten; Lorusso, Pierdomenico; Papukchiev, Angel
Opublikowane w: Numer 1, 2018
Wydawca: American Society of Mechanical Engineers / International Conference on Nuclear Engineering, Proceedings, ICONE
DOI: 10.1115/ICONE2681434

Phénix Transient Analysis for the Assessment of RELAP5-3D Based on Dissymmetric Test Benchmark

Autorzy: F. Giannetti, V. Narcisi, A. Subioli, A. Del Nevo
Opublikowane w: Volume 6B: Thermal-Hydraulics and Safety Analyses, 2018, Strona(/y) V06BT08A057, ISBN 978-0-7918-5149-4
Wydawca: ASME
DOI: 10.1115/ICONE26-82419

A fast algorithm for Direct Numerical Simulation of turbulent convection with immersed boundaries

Autorzy: D. Angeli, E. Stalio
Opublikowane w: Computers & Fluids, Numer 183, 2019, Strona(/y) 148-159, ISSN 0045-7930
Wydawca: Pergamon Press Ltd.
DOI: 10.1016/j.compfluid.2019.03.002

POD-Galerkin modeling of a heated pool

Autorzy: Jorge Yáñez Escanciano, Andreas G. Class
Opublikowane w: Progress in Nuclear Energy, Numer 113, 2019, Strona(/y) 196-205, ISSN 0149-1970
Wydawca: Elsevier BV
DOI: 10.1016/j.pnucene.2019.01.017

Pre-test analysis of accidental transients for ALFRED SGBT mock-up characterization

Autorzy: Vincenzo Narcisi, Fabio Giannetti, Alessandro Del Nevo, Mariano Tarantino, Gianfranco Caruso
Opublikowane w: Nuclear Engineering and Design, Numer 333, 2018, Strona(/y) 181-195, ISSN 0029-5493
Wydawca: Elsevier BV
DOI: 10.1016/j.nucengdes.2018.04.015

Direct numerical simulations for liquid metal applications

Autorzy: I. Tiselj, E. Stalio, D. Angeli, J. Oder
Opublikowane w: Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors, 2019, Strona(/y) 219-244, ISBN 9780-081019801
Wydawca: Elsevier
DOI: 10.1016/B978-0-08-101980-1.00016-8

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