Search results for "Thermal-hydraulic"

showing 10 items of 18 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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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 …

EFIT reactor RELAP5 thermal-hydraulic code protected accidental transientsEngineeringNuclear transmutationWaste managementbusiness.industryNuclear engineeringThermal power stationHeat sinkThermal hydraulicsNatural circulationDecay heatbusinessReactor pressure vesselSettore ING-IND/19 - Impianti NucleariThermal energyVolume 3: Thermal Hydraulics; Instrumentation and Controls
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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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THERMAL-HYDRAULIC STUDY IN SUPPORT OF THE DESIGN OF THE DEMO BALANCE OF PLANT

2020

The European Research Roadmap to the Realisation of Fusion Energy, foresees that the Demonstration Fusion Power Reactor (DEMO) is going to be the successor of ITER reactor in the pathway towards the exploitation of nuclear fusion to produce electric energy on an industrial scale. It will, hence, have to deliver hundreds MW of electric power ensuring an adequate availability and reliability of operation over a reasonable time span. EU-DEMO pre-conceptual design is being conducted by research institutions and universities from 26 countries of European Union, Switzerland and Ukraine, with the main aim to provide electric energy to the grid from nuclear fusion reactions by 2050. However, where …

Balance of PlantHeat ExchangerANSYS-CFXThermal-HydraulicRELAP5-3DDEMOSettore ING-IND/19 - Impianti Nucleari
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Hydraulic Analysis of Blanket Cooling System

2014

blanketITERthermal-hydraulicsSettore ING-IND/19 - Impianti Nucleari
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Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling

2022

Abstract Safety analyses for nuclear power plants were carried out in the past using a conservative approach. With the increase of the phenomenological knowledge, through experimental data, and computational power, it became possible to adopt best estimate thermal- hydraulic system codes to perform deterministic safety analyses. However, some uncertainties are still present in the models, correlations, initial and boundary conditions, etc. Therefore, it is fundamental to quantify the uncertainty of calculation. This approach is called “Best Estimate Plus Uncertainty” (BEPU). Among the available uncertainty analysis methodologies, the probabilistic method to propagate input uncertainty is wi…

HistoryThermal-hydraulicsSettore ING-IND/19 - Impianti NucleariComputer Science ApplicationsEducationJournal of Physics: Conference Series
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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…

Finite volume methodRELAP5Computer simulationMechanical EngineeringNuclear engineeringBlanketCoolantThermal hydraulicsblanketNuclear Energy and EngineeringThermal-hydraulicWater coolingThermal-hydraulic RELAP5 Draining BlanketEnvironmental scienceGeneral Materials ScienceTransient (oscillation)drainingSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringElectronic circuit
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Thermal-hydraulic analysis on the cooling system of the target in the SPES plant

2012

Settore ING-IND/19 - Impianti NucleariThermal-hydraulic analysis cooling system SPES
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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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