Search results for "Critical heat flux"

showing 3 items of 13 documents

Analysis of the steady state hydraulic behaviour of the ITER blanket cooling system

2015

Abstract The blanket system is the ITER reactor component devoted to providing a physical boundary for plasma transients and contributing to thermal and nuclear shielding of vacuum vessel, magnets and external components. It is expected to be subjected to significant heat loads under nominal conditions and its cooling system has to ensure an adequate cooling, preventing any risk of critical heat flux occurrence while complying with pressure drop limits. At the University of Palermo a study has been performed, in cooperation with the ITER Organization, to investigate the steady state hydraulic behaviour of the ITER blanket standard sector cooling system. A theoretical–computational approach …

Pressure dropFinite volume methodSteady stateITER Blanket HydraulicsCritical heat fluxMechanical EngineeringMass flowNuclear engineeringBlanketCoolantNuclear Energy and EngineeringWater coolingEnvironmental scienceGeneral Materials ScienceSettore ING-IND/19 - Impianti NucleariCivil and Structural Engineering
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Steady state and transient thermal–hydraulic analyses on ITER divertor module

2005

Abstract One of the most challenging components of ITER is the divertor devoted at controlling the characteristics of the plasma boundary, exhausting the α particles and reducing the impurities in the plasma. The thermal–hydraulic design of the divertor is particularly, demanding because of the high heat loads and the cooling flow margin in the plasma-facing components (PFCs). The pressure drop is limited by the pumping power and also avoiding the risk of reaching critical heat flux (CHF). Furthermore, for maintenance operation foreseen, each single divertor cassette should be drained and dried before withdrawing it out from the vacuum vessel. To address these requirements, European Fusion …

Pressure dropTokamakMaterials scienceCritical heat fluxHydraulicsMechanical EngineeringNuclear engineeringDivertorFusion powerSteady statelaw.inventionThermal hydraulicsNuclear physicsDivertorTransient thermal–hydraulicNuclear Energy and EngineeringHeat fluxlawITERRELAP codeGeneral Materials ScienceSettore ING-IND/19 - Impianti NucleariCivil and Structural EngineeringFusion Engineering and Design
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Experimental and Numerical Simulations of Flow and Heat Transfer in Heat Exchanger Elements Using Liquid Crystal Thermography

2004

Experimental and numerical investigation of heat transfer and fluid flow were conducted for classic heat exchanger elements (flat plate with fin-tubes in-line, staggered and with vortex generators) and corrugated-undulated ducts under transitional and weakly turbulent conditions. The dependence of average heat transfer and pressure drop on Reynolds number and geometrical parameters was investigated. Distributions of local heat transfer coefficient were obtained by using liquid crystal thermography and surface-averaged values were computed. Three-dimensional numerical simulations were conducted by a finite-volume method using a low-Reynolds number k-e model under the assumption of fully deve…

Thermal scienceDynamic scraped surface heat exchangerMaterials scienceThermochromic Liquid CrystalCritical heat fluxHeat transfer enhancementThermodynamicsMechanicsHeat transfer coefficientCondensed Matter PhysicsHeat TransferChurchill–Bernstein equationPhysics::Fluid DynamicsThermographyHeat transferPlate Heat ExchangerMicro heat exchangerFluid FlowSettore ING-IND/19 - Impianti Nucleari
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