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Rozvoj inverzních úloh vedení tepla řešených s využitím optimalizačních postupů a vysokého stupně paralelizace / Development of inverse tasks solved by using the optimizing procedures and large number of parallel threadsOndroušková, Jana Unknown Date (has links)
In metallurgy it is important to know a cooling efficiency of a product as well as cooling efficiency of working rolls to maximize the quality of the product and to achieve the long life of working rolls. It is possible to examine this cooling efficiency by heat transfer coefficients and surface temperatures. The surface temperature is hardly measured during the cooling. It is better to compute it together with heat transfer coefficient by inverse heat conduction problem. The computation is not easy and it uses estimated values which are verified by direct heat conduction problem. The time-consuming of this task can be several days or weeks, depends on the complexity of the model. Thus there are tendencies to shorten the computational time. This doctoral thesis considers the possible way of the computing time shortening of inverse heat conduction problem, which is the parallelization of this task and its transfer to a graphic card. It has greater computing power than the central processing unit (CPU). One computer can have more compute devices. That is why the computing time on different types of devices is compared in this thesis. Next this thesis deals with obtaining of surface temperatures for the computation by infrared line scanner and using of inverse heat conduction problem for the computing of the surface temperature and heat transfer coefficient during passing of a test sample under cooling section and cooling by high pressure nozzles.
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Estudo experimental da ebulição de hidrocarbonetos em tubo de multi mini canaisSilva, Priscila Forgiarini da 06 November 2017 (has links)
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Previous issue date: 2017-11-06 / CAPES - Coordenação de Aperfeiçoamento de Pessoal de Nível Superior / PROSUP - Programa de Suporte à Pós-Gradução de Instituições de Ensino Particulares / Este trabalho apresenta um estudo experimental da transferência de calor e queda de pressão na ebulição do isobutano, R600a, e do propano, R290, em um tubo composto por sete mini canais paralelos, cujo diâmetro hidráulico é de 1,47 mm. Os testes em ebulição foram realizados com uma temperatura de saturação de 20 ºC, para ambos os fluidos refrigerantes e pressão de saturação de 300 kPa, para o R600a e de 840 kPa para o R290, com velocidades mássicas entre 35 e 170 kg/(m²s) e fluxos de calor na seção de testes entre 5,3 e 21 kW/m². De acordo com os testes realizados verificou-se que o coeficiente de transferência de calor, para ambos os fluidos refrigerantes, aumenta conforme o incremento do fluxo de calor e velocidade mássica. O coeficiente de transferência de calor atingiu valores entre 1 a 18 kW/(m²K) para o R290 e de 1 a 9 kW/(m²K) para o R600a. A queda de pressão aumentou com o incremento da velocidade mássica e título de vapor em todos os testes, enquanto que o fluxo de calor apresentou influência na queda de pressão apenas nas maiores velocidades mássicas. Observou-se que a queda de pressão por aceleração apresenta a menor parcela, enquanto que, a queda de pressão por atrito apresenta a maior parcela. Na comparação entre o R290 e o R600a, verificou-se que o isobutano apresenta maior queda de pressão. Também foram analisados os padrões de escoamento, sendo observados os padrões de bolhas isoladas, pistonado, agitado, anular ondulado e anular, sendo que o padrão de bolhas isoladas foi observado somente para o R290, e o padrão anular mostrou-se presente para títulos superiores a 0,4. / This work presents an experimental study of heat transfer and pressure drop in boiling of isobutane, R600a, and propane, R290, in a tube composed of seven parallel mini channels, whose hydraulic diameter is 1.47 mm. Boiling tests were performed with a saturation temperature of 20 ºC for both refrigerants and saturation pressure of 300 kPa for R600a and 840 kPa for R290, with mass velocities between 35 and 170 kg/(m²s) and heat flux in the test section between 5.3 and 21 kW/m². According to the tests performed it was verified that the heat transfer coefficient for both refrigerant fluids increases as the heat flux and mass velocity increase. The heat transfer coefficient reached values between 1-18 kW/(m²K) for the R290 and 1-9 kW/(m²K) for the R600a. The pressure drop increased with increasing mass velocity and vapor quality in all tests, while the heat flux showed influence on the pressure drop only at higher mass velocities. It was observed that the pressure drop by acceleration presents the smallest portion, while the friction presents the largest portion. In the comparison between R290 and R600a, it was found that isobutane showed a higher pressure drop. Flow patterns were also analyzed, with isolated bubble, piston, agitated, annular and annular bubble patterns being observed, and the isolated bubble pattern was observed only for R290, and the annular pattern was present for quality higher than 0.4.
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Modeling of Heat TransferWahlberg, Tobias January 2011 (has links)
Modeling of heat transfer using Dymola. In this report a evaporator, economizer and superheater where modeled. The report describes how the models where modeled and what input was most suitable for a accurate model.
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Engineering nanomaterials with enhanced functionalityLi, Shanghua January 2006 (has links)
<p>This thesis deals with the engineering of novel nanomaterials, particularly nanocomposites and nanostructured surfaces with enhanced functionalities. The study includes two parts; in the first part, an in situ sol-gel polymerization approach is used for the synthesis of polymer-inorganic hybrid material and its exceptional transparent UV-shielding effect has been investigated. In the second part, electrodeposition process has been adapted to engineer surfaces and the boiling performance of the fabricated nanostructured surfaces is evaluated.</p><p>In the first part of the work, polymer-inorganic hybrid materials composed of poly(methylmethacrylate) (PMMA) and zinc compounds were prepared by in situ sol-gel transition polymerization of zinc complex in PMMA matrix. The immiscibility of heterophase of solid organic and inorganic constituents was significantly resolved by an in situ sol-gel transition polymerization of ZnO nanofillers within PMMA in the presence of dual functional agent, monoethanolamine, which provided strong secondary interfacial interactions for both complexing and crosslinking of constituents.</p><p>In the second part of the work, nanoengineering on the surface of copper plates has been performed in order to enhance the boiling heat transfer coefficient. Micro-porous surfaces with dendritic network of copper nanoparticles have been obtained by electrodeposition with dynamic templates. To further alter the grain size of the dendritic branches, the nanostructured surfaces underwent a high temperature annealing treatment.</p><p>Comprehensive characterization methods of the polymer-inorganic hybrid materials and nanoengineered surfaces have been undertaken. XRD, 1H NMR, FT-IR, TGA, DSC, UV-Vis, ED, SEM, TEM and HRTEM have been used for basic physical properties. Pool boiling tests were performed to evaluate the boiling performance of the electrodeposited nanostructured micro-porous structures.</p><p>The homogeneous PZHM exhibited enhanced UV-shielding effects in the entire UV range even at very low ZnO content of 0.02 wt%. Moreover, the relationship between band gap and particle size of incorporated ZnO by sol-gel process was in good agreement with the results calculated from the effective mass model between bandgap and particle size. The fabricated enhanced surface has shown an excellent performance in nucleate boiling. At heat flux of 1 W/cm2, the heat transfer coefficient is enhanced over 15 times compared to a plain reference surface. A model has been presented to explain the enhancement based on the structure characteristics.</p>
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Development, validation and application of an effective convectivity model for simulation of melt pool heat transfer in a light water reactor lower headTran, Chi Thanh January 2007 (has links)
<p>Severe accidents in a Light Water Reactor (LWR) have been a subject of the research for the last three decades. The research in this area aims to further understanding of the inherent physical phenomena and reduce the uncertainties surrounding their quantification, with the ultimate goal of developing models that can be applied to safety analysis of nuclear reactors. The research is also focusing on evaluation of the proposed accident management schemes for mitigating the consequences of such accidents.</p><p>During a hypothetical severe accident, whatever the scenario, there is likelihood that the core material will be relocated and accumulated in the lower plenum in the form of a debris bed or a melt pool. Physical phenomena involved in a severe accident progression are complex. The interactions of core debris or melt with the reactor structures depend very much on the debris bed or melt pool thermal hydraulics. That is why predictions of heat transfer during melt pool formation in the reactor lower head are important for the safety assessment.</p><p>The main purpose of the present study is to advance a method for describing turbulent natural convection heat transfer of a melt pool, and to develop a computational platform for cost-effective, sufficiently-accurate numerical simulations and analyses of Core Melt-Structure-Water Interactions in the LWR lower head during a postulated severe core-melting accident.</p><p>Given the insights gained from Computational Fluid Dynamics (CFD) simulations, a physics-based model and computationally-efficient tools are developed for multi-dimensional simulations of transient thermal-hydraulic phenomena in the lower plenum of a Boiling Water Reactor (BWR) during the late phase of an in-vessel core melt progression. A model is developed for the core debris bed heat up and formation of a melt pool in the lower head of the reactor vessel, and implemented in a commercial CFD code. To describe the natural convection heat transfer inside the volumetrically decay-heated melt pool, we advanced the Effective Convectivity Conductivity Model (ECCM), which was previously developed and implemented in the MVITA code. In the present study, natural convection heat transfer is accounted for by only the Effective Convectivity Model (ECM). The heat transport and interactions are represented through an energy-conservation formulation. The ECM then enables simulations of heat transfer of a high Rayleigh melt pool in 3D large dimension geometry.</p><p>In order to describe the phase-change heat transfer associated with core debris, a temperature-based enthalpy formulation is employed in the ECM (the phase-change ECM or so called the PECM). The PECM is capable to represent possible convection heat transfer in a mushy zone. The simple approach of the PECM method allows implementing different models of the fluid velocity in a mushy zone for a non-eutectic mixture. The developed models are validated by a dual approach, i.e., against the existing experimental data and the CFD simulation results.</p><p>The ECM and PECM methods are applied to predict thermal loads to the vessel wall and Control Rod Guide Tubes (CRGTs) during core debris heat up and melting in the BWR lower plenum. Applying the ECM and PECM to simulations of reactor-scale melt pool heat transfer, the results of the ECM and PECM calculations show an apparent effectiveness of the developed methods that enables simulations of long term accident transients. It is also found that during severe accident progression, the cooling by water flowing inside the CRGTs plays a very important role in reducing the thermal load on the reactor vessel wall. The results of the CFD, ECM and PECM simulations suggest a potential of the CRGT cooling as an effective mitigative measure during a severe accident progression.</p>
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The Effective Convectivity Model for Simulation and Analysis of Melt Pool Heat Transfer in a Light Water Reactor Pressure Vessel Lower HeadTran, Chi Thanh January 2009 (has links)
Severe accidents in a Light Water Reactor (LWR) have been a subject of intense research for the last three decades. The research in this area aims to reach understanding of the inherent physical phenomena and reduce the uncertainties in their quantification, with the ultimate goal of developing models that can be applied to safety analysis of nuclear reactors, and to evaluation of the proposed accident management schemes for mitigating the consequences of severe accidents. In a hypothetical severe accident there is likelihood that the core materials will be relocated to the lower plenum and form a decay-heated debris bed (debris cake) or a melt pool. Interactions of core debris or melt with the reactor structures depend to a large extent on the debris bed or melt pool thermal hydraulics. In case of inadequate cooling, the excessive heat would drive the structures' overheating and ablation, and hence govern the vessel failure mode and timing. In turn, threats to containment integrity associated with potential ex-vessel steam explosions and ex-vessel debris uncoolability depend on the composition, superheat, and amount of molten corium available for discharge upon the vessel failure. That is why predictions of transient melt pool heat transfer in the reactor lower head, subsequent vessel failure modes and melt characteristics upon the discharge are of paramount importance for plant safety assessment. The main purpose of the present study is to develop a method for reliable prediction of melt pool thermal hydraulics, namely to establish a computational platform for cost-effective, sufficiently-accurate numerical simulations and analyses of core Melt-Structure-Water Interactions in the LWR lower head during a postulated severe core-melting accident. To achieve the goal, an approach to efficient use of Computational Fluid Dynamics (CFD) has been proposed to guide and support the development of models suitable for accident analysis. The CFD method, on the one hand, is indispensable for scrutinizing flow physics, on the other hand, the validated CFD method can be used to generate necessary data for validation of the accident analysis models. Given the insights gained from the CFD study, physics-based models and computationally-efficient tools are developed for multi-dimensional simulations of transient thermal-hydraulic phenomena in the lower plenum of a LWR during the late phase of an in-vessel core melt progression. To describe natural convection heat transfer in an internally heated volume, and molten metal layer heated from below and cooled from the top (and side) walls, the Effective Convectivity Models (ECM) are developed and implemented in a commercial CFD code. The ECM uses directional heat transfer characteristic velocities to transport the heat to cooled boundaries. The heat transport and interactions are represented through an energy-conservation formulation. The ECM then enables 3D heat transfer simulations of a homogeneous (and stratified) melt pool formed in the LWR lower head. In order to describe phase-change heat transfer associated with core debris or binary mixture (e.g. in a molten metal layer), a temperature-based enthalpy formulation is employed in the Phase-change ECM (so called the PECM). The PECM is capable to represent natural convection heat transfer in a mushy zone. Simple formulation of the PECM method allows implementing different models of mushy zone heat transfer for non-eutectic mixtures. For a non-eutectic binary mixture, compositional convection associated with concentration gradients can be taken into account. The developed models are validated against both existing experimental data and the CFD-generated data. ECM and PECM simulations show a superior computational efficiency compared to the CFD simulation method. The ECM and PECM methods are applied to predict thermal loads imposed on the vessel wall and Control Rod Guide Tubes (CRGTs) during core debris heatup and melting in a Boiling Water Reactor (BWR) lower plenum. It is found that during the accident progression, the CRGT cooling plays a very important role in reducing the thermal loads on the reactor vessel wall. Results of the ECM and PECM simulations suggest a high potential of the CRGT cooling to be an effective measure for severe accident management in BWRs. / <p>QC 20100812</p>
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Desenvolvimento e caracterização de compósitos sanduíche para isolamento térmicoSartori, Ana Paola 26 October 2009 (has links)
Um painel sanduíche consiste essencialmente em duas faces, podendo inclusive possuir reforços metálicos e um núcleo formado normalmente por um polímero celular. As faces deste tipo de painel podem estar unidas por um adesivo estrutural, ou por espuma rígida de poliuretano (PU) injetado diretamente sobre os substratos, quando a união ocorrerá naturalmente. A propriedade de maior relevância que o painel sanduíche deve ter para o transporte de cargas congeladas (0ºC a -30ºC) ou refrigeradas (7ºC a 1ºC) é a condutividade térmica (k). Dentro deste contexto o objetivo deste trabalho foi propor e caracterizar painéis sanduíches que possam ser utilizados em câmaras frigoríficas. Este trabalho apresenta as seguintes alternativas para compósito sanduíche: amostra 1 (PRFV/PU/PRFV); amostra 2 (AG/PU/AG); amostra 3 (Frisado/PU/PRFV); e amostra 4 (Al/PU/Al), onde PRFV é poliéster reforçado com fibra de vidro, PU é espuma rígida de poliuretano, AG é aço galvanizado, Frisado é alumínio frisado, e Al é alumínio. Estes painéis foram caracterizados quanto às propriedades físico-mecânicas, térmicas, morfológicas e custo. Foi possível concluir que o sistema (AG/PU/AG) mostrou o melhor custo versus desempenho dentre os compósitos propostos. / Submitted by Marcelo Teixeira (mvteixeira@ucs.br) on 2014-05-29T19:30:53Z
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Dissertacao Ana Paola Sartori.pdf: 3882091 bytes, checksum: c7530ac27f11dffba880ed97ee828f31 (MD5) / A sandwich panel consists essentially of two face sheets and may even have metal reinforcements and a core formed, usually by a cellular polymer. The faces of this type of panel may be joined by a structural adhesive or in cases where the core is a rigid polyurethane foam injected directly on the substrates the union will occur naturally. The most relevant property of the sandwich panels for the transport of frozen (0ºC a -30ºC) or chilled (7ºC a 1ºC) cargo is thermal conductivity (k). Within this context the objective of this work is to obtain and characterize sandwich panels which can be used in refrigerated chambers. This work presents four alternatives for composite sandwich, sample 1 (PRFV/PU/PRFV), sample 2 (AG/PU/AG), sample 3 (Al Crimpy/PU/PRFV) and sample 4 (Al /PU/Al), were PRFV is a glass fibre reinforced plastics, PU is a rigid polyurethane, AG is galvanized steel, Al Crimpy is crimpy aluminum and Al is aluminum. These composites were characterized by physicalmechanical, thermal, morphologic and cost. It could be concluded that the AG/PU/AG showed the best cost versus performance.
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Contribution à l'étude des propriétés thermiques et hydrodynamiques d'un écoulement d'hélium normal (5HeI) diphasique en circulation naturelle pour le refroidissement des aimants supraconducteurs / Contribution to the study of thermal and hydrodynamical properties of HeI two phase natural circulation flow for cooling superconducting magnetsBenkheira, Lahcène 29 June 2007 (has links)
La méthode de refroidissement basée sur le principe thermosiphon présente un grand intérêt en raison de sa simplicité, de sa nature passive et de son coût faible. Elle est adoptée pour le refroidissement à 4,5 K de l’aimant supraconducteur du détecteur de particules CMS auprès du LHC en construction au CERN à Genève. Le travail présenté dans cette thèse étudie expérimentalement les propriétés thermiques et hydrodynamiques d’un écoulement d’He I diphasique en circulation naturelle. Le dispositif expérimental utilisé consiste en une boucle thermosiphon monobranche composée principalement d’un séparateur de phases, d’un tube descendant et d’une section d’essai. Les expériences ont été réalisées en faisant varier plusieurs paramètres tels que le diamètre des sections d’essai (10 mm ou 14 mm) et le flux de chaleur allant jusqu’à l’apparition de la crise d’ébullition. Ces expériences ont permis de déterminer les lois d’évolution des différentes grandeurs caractérisant l’écoulement (le débit massique de circulation, le débit massique vapeur, le titre massique, le coefficient de friction et le coefficient d’échange thermique) en fonction de la densité du flux de chaleur appliquée. Au regard des résultats obtenus, nous discutons la validité des différents modèles classiques existants dans la littérature. Nous montrons que le modèle homogène est le modèle le mieux adapté pour prédire les propriétés hydrodynamiques de ce type d’écoulement dans la gamme de titre massique 0?x?30%. De plus, nous proposons deux modèles pour la prédiction du coefficient de transfert de chaleur diphasique et la densité de flux de chaleur critique. Le premier considère que les effets de la convection forcée et de l’ébullition nucléée agissent simultanément et contribuent au transfert de chaleur. Le deuxième corrèle la densité de flux de chaleur critique mesurée en fonction du rapport altitude sur diamètre / The method of cooling based on the thermosiphon principle is of great interest because of its simplicity, its passivity and its low cost. It is adopted to cool down to 4,5 K the superconducting magnet of the CMS particles detector of the Large Hadron Collider (LHC) experiment under construction at CERN, Geneva. This work studies heat and mass transfer characteristics of two phase He I in a natural circulation loop. The experimental set-up consists of a thermosiphon single branch loop mainly composed of a phase separator, a downward tube, and a test section. The experiments were conducted with varying several parameters such as the diameter of the test section (10 mm or 14 mm) and the applied heat flux up to the appearance of the boiling crisis. These experiments have permitted to determine the laws of evolution of the various parameters characterizing the flow (circulation mass flow rate, vapour mass flow rate, vapour quality, friction coefficient, two phase heat transfer coefficient and the critical heat flux) as a function of the applied heat flux. On the base of the obtained results, we discuss the validity of the various existing models in the literature. We show that the homogeneous model is the best model to predict the hydrodynamical properties of this type of flow in the vapour quality range 0?x?30%. Moreover, we propose two models for the prediction of the two phase heat transfer coefficient and the density of the critical heat flux. The first one considers that the effects of the forced convection and nucleate boiling act simultaneously and contribute to heat transfer. The second one correlates the measured critical heat flux density with the ratio altitude to diameter
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Desenvolvimento e caracterização de compósitos sanduíche para isolamento térmicoSartori, Ana Paola 26 October 2009 (has links)
Um painel sanduíche consiste essencialmente em duas faces, podendo inclusive possuir reforços metálicos e um núcleo formado normalmente por um polímero celular. As faces deste tipo de painel podem estar unidas por um adesivo estrutural, ou por espuma rígida de poliuretano (PU) injetado diretamente sobre os substratos, quando a união ocorrerá naturalmente. A propriedade de maior relevância que o painel sanduíche deve ter para o transporte de cargas congeladas (0ºC a -30ºC) ou refrigeradas (7ºC a 1ºC) é a condutividade térmica (k). Dentro deste contexto o objetivo deste trabalho foi propor e caracterizar painéis sanduíches que possam ser utilizados em câmaras frigoríficas. Este trabalho apresenta as seguintes alternativas para compósito sanduíche: amostra 1 (PRFV/PU/PRFV); amostra 2 (AG/PU/AG); amostra 3 (Frisado/PU/PRFV); e amostra 4 (Al/PU/Al), onde PRFV é poliéster reforçado com fibra de vidro, PU é espuma rígida de poliuretano, AG é aço galvanizado, Frisado é alumínio frisado, e Al é alumínio. Estes painéis foram caracterizados quanto às propriedades físico-mecânicas, térmicas, morfológicas e custo. Foi possível concluir que o sistema (AG/PU/AG) mostrou o melhor custo versus desempenho dentre os compósitos propostos. / A sandwich panel consists essentially of two face sheets and may even have metal reinforcements and a core formed, usually by a cellular polymer. The faces of this type of panel may be joined by a structural adhesive or in cases where the core is a rigid polyurethane foam injected directly on the substrates the union will occur naturally. The most relevant property of the sandwich panels for the transport of frozen (0ºC a -30ºC) or chilled (7ºC a 1ºC) cargo is thermal conductivity (k). Within this context the objective of this work is to obtain and characterize sandwich panels which can be used in refrigerated chambers. This work presents four alternatives for composite sandwich, sample 1 (PRFV/PU/PRFV), sample 2 (AG/PU/AG), sample 3 (Al Crimpy/PU/PRFV) and sample 4 (Al /PU/Al), were PRFV is a glass fibre reinforced plastics, PU is a rigid polyurethane, AG is galvanized steel, Al Crimpy is crimpy aluminum and Al is aluminum. These composites were characterized by physicalmechanical, thermal, morphologic and cost. It could be concluded that the AG/PU/AG showed the best cost versus performance.
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External Heat Transfer Coefficient Predictions on a Transonic Turbine Nozzle Guide Vane Using Computational Fluid DynamicsEnico, Daniel January 2021 (has links)
The high turbine inlet temperature of modern gas turbines poses a challenge to the material used in the turbine blading of the primary stages. Mechanical failure mechanisms are more pronounced at these high temperatures, setting the lifetime of the blade. It is therefore crucial to obtain accurate local metal temperature predictions of the turbine blade. Accurately predicting the external heat transfer coefficient (HTC) distribution of the blade is therefore of uttermost importance. At present time, Siemens Energy uses the boundary layer code TEXSTAN for this purpose. The limitations coupled to such codes however make them less applicable for the complex flow physics involved in the hot gas path of turbine blading. The thesis therefore aims at introducing CFD for calculating the external HTC. This includes conducting an extensive literature study to find and validate a suitable methodology. The literature study was centered around RANS modeling, reviewing how the calculation of the HTC has evolved and the performance of some common turbulence and transition models. From the literature study, the SST k − ω model in conjunction with the γ − Reθ transition model, the v2 − f model and the Lag EB k − ε model were chosen for the investigation of a suitable methodology. The validation of the methodology was based on the extensively studied LS89 vane linear cascade of the von Karman Institute. In total 13 test cases of the cascade were chosen to represent a wide range of flow conditions. Both a periodic model and a model of the entire LS89 cascade were tested but there were great uncertainties whether or not the correct flow conditions were achieved with the model of the entire cascade. It was therefore abandoned and a periodic model was used instead. The decay of turbulence intensity is not known in the LS89 cascade. This made the case difficult to model since the turbulence boundary conditions then were incomplete. Two approaches were attempted to handle this deficiency, where one was ultimately found invalid. It was recognized that the Steelant-Dick postulation could be used in order to find a turbulent length scale which when specified at the inlet, lead to fairly good agreement with data of the HTC. The validation showed that the SST γ − Reθ model performs relatively well on the suction side and in transition onset predictions but worse on the pressure side for certain flow conditions. The v2 − f model performed better on the pressure side and on a small portion of the suction side. Literature emphasized the importance of obtaining proper turbulence characteristics around the vane for accurate HTC-predictions. It was found that the results of the validation step could be closely coupled to this statement and that further work is needed regarding this. Further research must also be done on the Steelant-Dick postulation to validate it as a reliable method in prescribing the inlet length scale.
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