Search results for " Thermal-hydraulics"

showing 7 items of 7 documents

Analysis of a full-scale integral test in PERSEO facility by using TRACE code

2017

Over the last decades a lot of experimental researches have been done to increase the reliability of passive decay heat removal systems implementing in-pool immersed heat exchanger. In this framework, a domestic research program on innovative safety systems was carried out leading the design and the development of the PERSEO facility at the SIET laboratories. The configuration of the system consists of an heat exchanger contained in a small pool which is connected both at the bottom and at the top to a large water reservoir pool. Within the frame of a national research program funded by the Italian minister of economic development, the DEIM department of the University of Palermo in coopera…

HistoryPERSEO Validation TRACE Thermal-hydraulics Passive safety systemsPhysics -- ExperimentsHeat exchangersComputer scienceNuclear engineeringFrame (networking)Full scaleExperimental dataSystem safetyComputer Science ApplicationsEducationThermal hydraulicsEconomic development -- ItalyHeat exchangerDecay heatTRACE (psycholinguistics)
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On a computational study of the hydraulic behavior of the ITER divertor cassette full-scale prototype

2009

NUCLEAR FUSION DIVERTOR THERMAL-HYDRAULICS
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Hydraulic Analysis of the CDR Design of the ITER TBM Port Plug

2013

NUCLEAR FUSION TBM PORT PLUG THERMAL-HYDRAULICSSettore ING-IND/19 - Impianti Nucleari
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On the numerical assessment of the thermal-hydraulic behaviour of ITER Upper Port Plug Main Body cooling circuit

2010

ITER draining and drying thermal-hydraulicsSettore ING-IND/19 - Impianti Nucleari
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The hydraulic behaviour of the prototype of on a ITER divertor cassette

2009

Settore ING-IND/19 - Impianti NucleariITER divertor thermal-hydraulics
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Steady state and transient thermal-hydraulic characterization of full-scale ITER divertor plasma facing components

2008

Abstract In the frame of the activities related to ITER divertor R&D, ENEA CR Brasimone was in charge by EFDA (European Fusion Development Agreement) to investigate the thermal-hydraulic behaviour of the full-scale divertor plasma facing components, i.e. the outer vertical target, the inner vertical target and the dome-liner, both in steady state and during draining and drying transient. The investigation was performed by means of both experimental test campaigns performed at ENEA CR Brasimone and theoretical simulation developed in RELAP5 Mod.3.3 environment at the Department of Nuclear Engineering of the University of Palermo (DIN). This paper presents the achieved experimental results fo…

Materials scienceSteady stateITER Divertor Plasma facing components Thermal-hydraulicsMechanical EngineeringNuclear engineeringDivertorFull scalePlasmaThermal hydraulicsNuclear Energy and EngineeringFUSIONE NUCLEARE ITER DIVERTORE TERMOIDRAULICAGeneral Materials ScienceTransient (oscillation)Settore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Analysis of the SPES-3 direct vessel injection line break by using TRACE code

2011

TRACE Code thermal-hydraulicsSettore ING-IND/19 - Impianti Nucleari
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