ENEA-IRIS Open Archive è l’archivio della produzione scientifica dell'ENEA, realizzato con l'obiettivo di raccogliere, catalogare e rendere facilmente accessibili in rete i risultati della ricerca. Gli autori dell’ENEA provvedono a depositare le proprie pubblicazioni (articoli su rivista, presentazioni a congressi, report, ecc.). In particolare, quelle finanziate dalla Commissione Europea nell’ambito del programma H2020 (che prevede il deposito obbligatorio in un Repository), una volta caricate, vengono automaticamente importate dal portale europeo OpenAIRE. È possibile inserire, o importare direttamente dalle banche dati previste, le informazioni descrittive del documento e anche allegare, ove consentito dalla normativa sul diritto d'autore, il testo completo della pubblicazione.

ENEA-IRIS Open Archive utilizza la piattaforma IRIS (Institutional Research Information System) sviluppata da CINECA.

ENEA is setting up, applying and validating numerical models and an integrated multi-physics approach, based on existing codes and aimed at supporting safety analysis of liquid metal Gen. IV fast reactors. The paper provides an outline of the activity and it is focused on qualification of a three-dimensional thermal- hydraulic model of EBR-II primary and secondary systems using the system code RELAP5-3DO. The nodalization models one by one the fuel assemblies of the core and of the extended core of the reactor for an easy and efficient coupling with a 3D neutron kinetic code. The paper presents the qualification of the nodalization based on the EBR-II test SHRT-17. The analysis of the experimental data, the identification of the thermal-hydraulics phenomena observed in the tests are the basis for assessing the code performances and for discussing its limitations. © Copyright (2015) by American Nuclcar Society All rights reserved.

Qualification of a RELAP5-3D © system code nodalization of EBR-II

Del Nevo, A.
2015-01-01

Abstract

ENEA is setting up, applying and validating numerical models and an integrated multi-physics approach, based on existing codes and aimed at supporting safety analysis of liquid metal Gen. IV fast reactors. The paper provides an outline of the activity and it is focused on qualification of a three-dimensional thermal- hydraulic model of EBR-II primary and secondary systems using the system code RELAP5-3DO. The nodalization models one by one the fuel assemblies of the core and of the extended core of the reactor for an easy and efficient coupling with a 3D neutron kinetic code. The paper presents the qualification of the nodalization based on the EBR-II test SHRT-17. The analysis of the experimental data, the identification of the thermal-hydraulics phenomena observed in the tests are the basis for assessing the code performances and for discussing its limitations. © Copyright (2015) by American Nuclcar Society All rights reserved.
2015
9781510811843
Fast reactors;System thermal-hydraulics;RELAP5-3D©;EBR-II
4.1 Contributo in Atti di convegno
File in questo prodotto:
Non ci sono file associati a questo prodotto.

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/20.500.12079/3503
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
social impact