Search results for " RELAP5"
showing 7 items of 7 documents
ANALISI DI SICUREZZA DI SISTEMI DELL’IMPIANTO SPES
2014
Il progetto SPES prevede il bombardamento di un bersaglio in carburo di uranio con un fascio di protoni, in modo da generare, tramite reazione nucleare, specie radioattive all’interno del target. Le particelle radioattive generate vengono successivamente estratte, ionizzate, separate in massa ed accelerate come fascio di ioni radioattivo. Il presente lavoro di tesi ha riguardato lo studio di sicurezza di alcune unità dell'impianto SPES e si inserisce nell'ambito di una collaborazione di ricerca tra i Laboratori Nazionali di Legnaro ed il Dipartimento dell'Energia, sezione Nucleare, dell'Università degli Studi di Palermo. Tale attività ha comportato l'analisi sui componenti del sistema di pr…
Thermalhydraulic analyses of overpower transients in the EFIT reactor
2008
Analysis of Protected Accidental Transients in the EFIT Reactor With the RELAP5 Thermal-Hydraulic Code
2008
The European Facility for Industrial Transmutation (EFIT) is aimed at demonstrating the feasibility of transmutation process through the Accelerator Driven System (ADS) route on an industrial scale. The conceptual design of this reactor of about 400 MW thermal power is under development in the frame of the European EUROTRANS Integrated Project of the EURATOM Sixth Framework Program (FP6). EFIT is a pool-type reactor cooled by forced circulation of lead in the primary system where the heat is removed by steam generators installed inside the reactor vessel. The reactor power is sustained by a spallation neutron source supplied by a proton beam impinging on a lead target at the core centre. A …
TRACE and RELAP5 Codes for Beyond Design Accident Condition Simulation in the SPES3 Facility
2012
Code validation on qualified experimental data is a fundamental issue in the design and safety analyses of nuclear power plants. The SPES3 facility is being built at the SIET laboratories for an integral type SMR simulation, in the frame of an R&D program on nuclear fission, funded by the Italian Ministry of Economic Development and led by ENEA. The facility, based on the IRIS reactor design, reproduces the primary, secondary and containment systems with 1:100 volume scale, full elevation and prototypical fluid and thermal-hydraulic conditions. It is suitable to test the plant response to design and beyond design accidents in order to verify the effectiveness of the primary and containm…
Numerical simulation of the transient thermal-hydraulic behaviour of the ITER blanket cooling system under the draining operational procedure
2015
Abstract Within the framework of the research and development activities supported by the ITER Organization on the blanket system issues, an intense analysis campaign has been performed at the University of Palermo with the aim to investigate the thermal-hydraulic behaviour of the cooling system of a standard 20° sector of ITER blanket during the draining transient operational procedure. The analysis has been carried out following a theoretical-computational approach based on the finite volume method and adopting the RELAP5 system code. In a first phase, attention has been focused on the development and validation of the finite volume models of the cooling circuits of the most demanding mod…