During the last decade the European activities in the field of nuclear fission research include the design of fast reactors cooled by liquid metals. Within this framework, the Fast REactor NEutronics/Thermal-hydraulICs (FRENETIC) code is being developed at Politecnico di Torino over the last few years. It implements a full-core coupled neutronic/thermalhydraulic model of a liquid-metal-cooled fast reactor as relevant for two of the six options currently under study within the framework of the Generation-IV International Forum, namely the lead-cooled fast reactors and the sodium-cooled fast reactors. The code validation process involves the participation in a coordinated research project of the International Atomic Energy Agency, aiming at testing different computational tools against the shutdown heat removal tests performed many years ago in the sodium-cooled Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory, USA. In this paper, results of the FRENETIC analysis of one of the transients considered in the project, the unprotected EBR-II shutdown heat removal test SHRT-45R, are presented and compared to the measurements, providing the first validation of the coupled neutronic/thermal-hydraulic features of the FRENETIC code.

Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient / Caron, Dominic; Bonifetto, Roberto; Dulla, Sandra; Mascolino, Valerio; Ravetto, Piero; Savoldi, Laura; Valerio, Domenico; Zanino, Roberto. - In: INTERNATIONAL JOURNAL OF ENERGY RESEARCH. - ISSN 0363-907X. - ELETTRONICO. - 42:1(2018), pp. 134-150. [10.1002/er.3571]

Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient

CARON, DOMINIC;BONIFETTO, ROBERTO;DULLA, SANDRA;RAVETTO, PIERO;SAVOLDI, LAURA;Valerio, Domenico;ZANINO, Roberto
2018

Abstract

During the last decade the European activities in the field of nuclear fission research include the design of fast reactors cooled by liquid metals. Within this framework, the Fast REactor NEutronics/Thermal-hydraulICs (FRENETIC) code is being developed at Politecnico di Torino over the last few years. It implements a full-core coupled neutronic/thermalhydraulic model of a liquid-metal-cooled fast reactor as relevant for two of the six options currently under study within the framework of the Generation-IV International Forum, namely the lead-cooled fast reactors and the sodium-cooled fast reactors. The code validation process involves the participation in a coordinated research project of the International Atomic Energy Agency, aiming at testing different computational tools against the shutdown heat removal tests performed many years ago in the sodium-cooled Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory, USA. In this paper, results of the FRENETIC analysis of one of the transients considered in the project, the unprotected EBR-II shutdown heat removal test SHRT-45R, are presented and compared to the measurements, providing the first validation of the coupled neutronic/thermal-hydraulic features of the FRENETIC code.
File in questo prodotto:
File Dimensione Formato  
J40_2016_IJER_FRENETIC_EBR_coupled_validation.pdf

non disponibili

Descrizione: Articolo principale
Tipologia: 2a Post-print versione editoriale / Version of Record
Licenza: Non Pubblico - Accesso privato/ristretto
Dimensione 4.81 MB
Formato Adobe PDF
4.81 MB Adobe PDF   Visualizza/Apri   Richiedi una copia
J40_2016_IJER_FRENETIC_EBR_coupled_validation_rev1-submitted.pdf

accesso aperto

Tipologia: 2. Post-print / Author's Accepted Manuscript
Licenza: Creative commons
Dimensione 3.23 MB
Formato Adobe PDF
3.23 MB Adobe PDF Visualizza/Apri
Pubblicazioni consigliate

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11583/2644045