Relevant bibliographies by topics / Thermo-hydraulic behaviour

Academic literature on the topic 'Thermo-hydraulic behaviour'

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Published: 14 March 2023

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Journal articles on the topic "Thermo-hydraulic behaviour"

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Ketelsen, Søren, Sebastian Michel, Torben O. Andersen, Morten Kjeld Ebbesen, Jürgen Weber, and Lasse Schmidt. "Thermo-Hydraulic Modelling and Experimental Validation of an Electro-Hydraulic Compact Drive." Energies 14, no. 9 (April 22, 2021): 2375. http://dx.doi.org/10.3390/en14092375.

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Electro-hydraulic compact drives (ECDs) are an emerging technology for linear actuation in a wide range of applications. Especially within the low power range of 5–10 kW, the plug-and-play capability, good energy efficiency and small space requirements of ECDs render this technology a promising alternative to replace conventional valve-controlled linear drive solutions. In this power range, ECDs generally rely on passive cooling to keep oil and system temperatures within the tolerated range. When expanding the application range to larger power classes, passive cooling may not be sufficient. Research investigating the thermal behaviour of ECDs is limited but indeed required for a successful expansion of the application range. In order to obtain valuable insights into the thermal behaviour of ECDs, thermo-hydraulic simulation is an important tool. This may enable system design engineers to simulate thermal behaviour and thus develop proper thermal designs during the early design phase, especially if such models contain few parameters that can be determined with limited information available. Our paper presents a lumped thermo-hydraulic model derived from the conservation of mass and energy. The derived model was experimentally validated based on experimental data from an ECD prototype. Results show good accuracy between measured and simulated temperatures. Even a simple thermal model containing only a few thermal resistances may be sufficient to predict steady-state and transient temperatures with reasonable accuracy. The presented model may be used for further investigations into the thermal behaviour of ECDs and thus toward proper thermal designs required to expand the application range.
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Guo, Shao Hua. "The Coupled Thermo-Hydro-Mechanical Behavior of Saturated Fractured Solids." Applied Mechanics and Materials 204-208 (October 2012): 123–27. http://dx.doi.org/10.4028/www.scientific.net/amm.204-208.123.

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The stress equilibrium equation of anisotropic solids, coupled to the hydrodynamic seepage equation and heat transfer equation of saturated fractured rocks, are studied here based on the standard space of physical presentation, in which an new thermo-hydro-elastic model is induced. A set of uncoupled equation of heat and hydraulic propagations in anisotropic saturated fractured rocks is deduced. From them, two new phenomena of heat and hydraulic propagation are obtained, which are affected by both anisotropic subspaces of solids and thermo-mechanical and hydro-mechanical coupling coefficients. Based on these laws, we discuss the heat and hydraulic wave behaviour for isotropic solids.
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Thomas, H. R., and P. J. Cleall. "Inclusion of expansive clay behaviour in coupled thermo hydraulic mechanical models." Engineering Geology 54, no. 1-2 (September 1999): 93–108. http://dx.doi.org/10.1016/s0013-7952(99)00065-4.

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Paulech, Juraj, Vladimír Kutiš, Gabriel Gálik, Jakub Jakubec, and Tibor Sedlár. "Thermo-Hydraulic Behaviour of Coolant in Nuclear Reactor VVER-440 Under Refuelling Conditions." Strojnícky casopis – Journal of Mechanical Engineering 67, no. 1 (April 1, 2017): 87–92. http://dx.doi.org/10.1515/scjme-2017-0009.

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Abstract The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in the VVER- 440 nuclear reactor under standard outage conditions. Heating-up and flow of coolant between the reactor pressure vessel and spent fuel storage pool are discussed.
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Singh, Sanjay K., Manish Mishra, and PK Jha. "Experimental investigations on thermo-hydraulic behaviour of triple concentric-tube heat exchanger." Proceedings of the Institution of Mechanical Engineers, Part E: Journal of Process Mechanical Engineering 229, no. 4 (April 16, 2014): 299–308. http://dx.doi.org/10.1177/0954408914531118.

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T’Joen, C., H. Huisseune, H. Canière, H. J. Steeman, A. Willockx, and M. De Paepe. "Interaction between mean flow and thermo-hydraulic behaviour in inclined louvered fins." International Journal of Heat and Mass Transfer 54, no. 4 (January 2011): 826–37. http://dx.doi.org/10.1016/j.ijheatmasstransfer.2010.10.020.

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Hashemi, Amirhossein, and Melis Sutman. "Thermo-hydro-mechanical behaviour of partially saturated fine-grained soils in the context of energy geostructures." Soils and Rocks 45, no. 1 (February 18, 2022): 1–17. http://dx.doi.org/10.28927/sr.2022.076821.

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The multi-physical phenomena, particularly water content and temperature variations, governing the behaviour of soils should be considered in the design and analysis of the energy geostructures. Soil temperature and water content variations impose a significant risk on the stability and serviceability of existing and future geostructures. Although potential failure modes, impacts at a system scale, and the response of saturated soils to thermal loads are previously discussed, interpretation of the thermo-hydro-mechanical behaviour of partially saturated soils in the context of energy geostructures is not thoroughly investigated. In this regard, this paper brings together the experimental data from several laboratory investigations to attain a comprehensive understanding of the partially saturated fine-grained soils response under thermo-hydro-mechanical loading, which plays a vital role in the analysis of the soil behaviour and energy geostructures in contact with them. In this paper, the effect of thermal loading in different matric suctions and hydraulic loading at different temperatures on soil preconsolidation stress, water content variation, thermal and hydraulic conductivities, and compression indexes are studied. Furthermore, soil thermal deformation is studied in detail for different overconsolidation ratios and matric suctions.
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Liu, Kui, Renato Zagorščak, Richard J. Sandford, Oliver N. Cwikowski, Alexander Yanushkevich, and Hywel R. Thomas. "Insights into the Thermal Performance of Underground High Voltage Electricity Transmission Lines through Thermo-Hydraulic Modelling." Energies 15, no. 23 (November 24, 2022): 8897. http://dx.doi.org/10.3390/en15238897.

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In this paper, a flexible numerical framework to provide thermal performance assessment for the underground buried cables, considering different geological and meteorological conditions, has been presented. Underground cables tend to retain the heat produced in the conductor, so complex coupled thermo-hydraulic response of the porous medium surrounding the cables needs to be assessed to prevent cable overheating and the associated reduction in cable capacity for carrying current. Applying a coupled thermo-hydraulic model within the developed numerical framework to conduct a health assessment on a subset of National Grid Electricity Transmission’s underground cables, this study provides novel insights into the thermal behaviour of buried circuits. The results indicate that backfill and surrounding native soil have the dominant effect on the thermal behaviour of cables, while the amount of precipitation and ambient temperature were found to have less impact on cable’s thermal behaviour. The findings strongly infer that the nature of the overloading which is undertaken in practice would have no ongoing negative impact, suggesting that more frequent or longer duration overloading regimes could be tolerated. Overall, this study demonstrates how the developed numerical framework could be harnessed to allow safe rating adjustments of buried transmission circuits.
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CUEVAS, J., M. VILLAR, M. MARTIN, J. COBENA, and S. LEGUEY. "Thermo-hydraulic gradients on bentonite: distribution of soluble salts, microstructure and modification of the hydraulic and mechanical behaviour." Applied Clay Science 22, no. 1-2 (November 2002): 25–38. http://dx.doi.org/10.1016/s0169-1317(02)00109-6.

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Ghidaglia, Jean-Michel. "Long time behaviour of solutions of abstract inequalities: Applications to thermo-hydraulic and magnetohydrodynamic equations." Journal of Differential Equations 61, no. 2 (February 1986): 268–94. http://dx.doi.org/10.1016/0022-0396(86)90121-x.

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Dissertations / Theses on the topic "Thermo-hydraulic behaviour"

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Castagna, Salvatore. "Thermo hydraulic behaviour of unstaturated salt aggregates." Doctoral thesis, Universitat Politècnica de Catalunya, 2007. http://hdl.handle.net/10803/6246.

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En el siglo pasado se ha desarrollado una nueva energía: la nuclear. Su aplicación comprende tanto el campo militar como el campo civil. Unos de los aspectos más interesantes es el uso de esta energía para la producción de electricidad de uso civil.
El combustible nuclear es de larga duración: unas barras de uranio pueden llegar a producir energía eléctrica durante una década aproximadamente. Sin embargo, a mediados del siglo pasado se planteó el problema de los residuos nucleares. Este problema es muy complejo por que, aunque la duración del combustible sea de una década, el periodo de decaimiento es del orden de siglos.
Esta tesis quiere aportar su granito de arena a esta nueva rama de la ciencia nuclear, estudiando algunos aspectos del comportamiento geotécnico de los agregados de sal, para su uso como material de relleno en los depósitos definitivos de los residuos nucleares de mayor peligrosidad.
La regla fundamental de diseño de dichos depósitos es que su función debe desarrollarse sin la ayuda del hombre o de máquinas y que la misma naturaleza tiene que ser quien proteja al hombre del riesgo de radiaciones durante el transcurso de los siglos.
Parece que al día de hoy la solución mundialmente aceptada es la de un depósito profundo en formaciones rocosas, a veces utilizando antiguas minas, incluso de sal. Se prevé que entre esta década y la próxima entrarán en funcionamiento varios de estos depósitos en los países en que la investigación en este área está más avanzada.
En Europa se está haciendo un esfuerzo común, bajo supervisión de la Unión Europea y por medio de proyectos de investigación, para estudiar el funcionamiento del almacenamiento y la difusión de los resultados de esos estudios entre los miembros de la Unión Europea, a fin de dar el mayor provecho a las diferentes investigaciones que en la actualidad se están desarrollando en todos los centros de investigación de Europa.
Esta tesis trata sobre el comportamiento termo hidráulico de los agregados de sal debido a las altas temperaturas que el decaimiento de los residuos nucleares produce. Este fenómeno crea unos efectos en los materiales de relleno y en la formación de base de alrededor del deposito.
La tesis tiene un desarrollo básicamente experimental. En el laboratorio se realizaron fundamentalmente dos ensayos; el primero permitió determinar la curva de retención de los agregados de sal altamente compactados. Para ello se utilizó la técnica de traslación de ejes para aplicar la succión matricial y se construyó una placa de succión apta a los materiales salinos para la realización de estos ensayos.
Este ensayo permitió determinar el comportamiento de una propiedad básica de los materiales salinos no saturados, sus resultados pudieron aplicarse al resto de los trabajos que se realizaron con posterioridad en esta tesis.
El objeto del segundo ensayo de laboratorio fue reproducir los fenómenos de variación de porosidad debidos a la presencia de una diferencia de temperatura en las extremidades de la muestra.
Dicho ensayo tiene una importancia fundamental para los almacenamientos profundos, porque los residuos radiactivos serán una fuente de calor durante varios siglos y la presencia de elevadas temperaturas induce fenómenos de flujo y transporte en el contacto con los contenedores de carburante nuclear agotado. Además, en el caso de los agregados de sal, a estos fenómenos cabe añadir el intercambio de sal entre la fase sólida y la líquida (precipitación /disolución).
Para desarrollar estas pruebas de laboratorio, se dedicó una parte importante de la investigación al desarrollo y comprobación del equipo de ensayo, siendo éste poco convencional y completamente novedoso. Este último ensayo, en su segunda fase, fue convalidado mediante un modelo numérico (CODE BRIGHT). Los resultados del modelo numérico han permitido confirmar todo cuanto se determinó en la fase experimental y la importancia de la succión matricial en estos fenómenos.
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Renard, Bertrand. "Thermo-Hydraulic behaviour of dual-channel superconducting Cable-In-Conduit Conductors for ITEER." Aix-Marseille 1, 2006. http://www.theses.fr/2006AIX11030.

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Afin d'optimiser le contrôle cryogénique des aimants supraconducteurs pour la fusion (ITER), les conducteurs de type câble en conduit à double canal (CICC) comprennent un canal central qui assure une résistance hydraulique minimale et une circulation d'hélium rapide. Le canal central constitué d'une spirale limite la température des supraconducteurs, mais complique singulièrement le refroidissement du câble. Les pertes de charge de la spirale centrale sont évaluées en azote puis en eau pressurisée ; un modèle de frottement hydraulique est ainsi proposé. Les températures doivent être connues dans le câble, afin de garantir le fonctionnement des supraconducteurs sous charge thermique. Il est alors possible de définir les marges et de fixer la température d'entrée. Des modèles 1D analytiques en régime permanent et transitoire ont été développés afin de mieux comprendre le couplage thermique entre les canaux du CICC. La mesure des constantes caractéristiques d'espace et de temps fournit une évaluation expérimentale de l'homogénéisation thermique interne. Un modèle simple et explicite du coefficient d'échange intercanal est proposé. Le risque de thermosiphon existant entre les deux canaux dans les parties verticales des bobines de fusion est évalué grâce à un critère. Les nouveaux modèles hydrauliques, thermiques et le critère de risque de thermosiphon permettent l'amélioration thermo-hydraulique de la spirale centrale de CICC
In an effort to optimise the cryogenics of large superconducting coils for fusion applications (ITER), dual channel Cable-In-Conduit Conductors (CICC) are designed with a central channel spiral to provide low hydraulic resistance and faster helium circulation. The qualitative and economic rationale of the conductor central channel is here justified to limit the superconductor temperature increase, but brings more complexity to the conductor cooling characteristics. The pressure drop of spirals is experimentally evaluated in nitrogen and water and an explicit hydraulic friction model is proposed. Temperatures in the cable must be quantified to guarantee superconductor margin during coil operation under heat disturbance and set adequate inlet temperature. Analytical one-dimensional thermal models, in steady state and in transient, allow to better understand the thermal coupling of CICC central and annular channels. The measurement of a heat transfer characteristic space and time constants provides cross-checking experimental estimations of the internal thermal homogenisation. A simple explicit model of global interchannel heat exchange coefficient is proposed. The risk of thermosiphon between the two channels is considered since vertical portions of fusion coils are subject to gravity. The new hydraulic model, heat exchange model and gravitational risk ratio allow the thermohydraulic improvement of CICC central spirals
Um die Kryogen-Benutzung und -Kontrolle der Supraleitenden Großmagneten für die Kernfusion (ITER) zu optimieren, wurde der Zweikanalrohrsupraleiterkabel (CICC) mit einer zentralen Spirale entworfen. Der Zentralkanal soll einen minimalen hydraulischen Widerstand und einen schnellen Heliumverkehr gewährleisten, führt jedoch zu einer schwierigeren Abkühlung des Kabels. Das qualitative und ökonomische Grundprinzip der Leiterspirale wird hier durch die Begrenzung der Supraleitertemperatur gerechtfertigt. Der Druckabfall der zentralen Spirale wird experimentell am Stickstoff und danach am Druckwasser ausgewertet und daraus ein hydraulisches Modell vorgeschlagen. Die Temperaturen im Kabel müssen quantitativ bekannt sein, um Hitzestörungen des Supraleiters während des Betriebes der Spule zu verhindern, sowie um ausreichende Spielräume mit entsprechend niedriger Eintrittstemperatur einzustellen. Es wurde analytische eindimensionale Modelle entwickelt, um die thermische Kopplung zwischen den Kanälen des CICC im Dauer- und Übergangszustand besser zu verstehen. Die Messung der Raum- und Zeit-Konstanten liefert eine Versuchsbewertung der internen thermischen Homogenisierung. Es wird ein einfaches und ausdrückliches Modell des globalen Zwischenkanal-Wärmeaustauschkoeffizienten vorgeschlagen. Das bestehende Thermosiphonrisiko zwischen den zwei Kanälen bei vertikale Fusionsspulen verweist auf ein Kriterium. Das neue hydraulische Modell, das Wärmeaustauschmodell und das Kriterium des Thermosiphonrisikos erlauben schließlich die thermohydraulische Optimierung der Kabel-Zentralspirale
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Cleall, Peter John. "An investigation of the thermo/hydraulic/mechanical behaviour of unsaturated soils, including expansive clays." Thesis, Cardiff University, 1998. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.389795.

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Ramesh, Anuradha Dharmavaram. "Modelling the thermo/hydraulic/mechanical behaviour of unsaturated soil using an elasto-plastic constitutive relationship." Thesis, Cardiff University, 1996. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.336542.

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Martínez-García, Elvira. "Experimental and numerical study on the thermo hydraulic behaviour in a wavy plate heat exchanger using Newtonian and non Newtonian fluids." Thesis, University of Bristol, 2002. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.271803.

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INSANA, ALESSANDRA. "Thermal and structural performance of energy tunnels." Doctoral thesis, Politecnico di Torino, 2020. http://hdl.handle.net/11583/2839836.

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Giraudon, Rémi. "Contribution to the manufacturing and the understanding of the thermal behaviour of capillary structures dedicated to Loop Heat Pipes." Thesis, Lyon, 2018. http://www.theses.fr/2018LYSEI003/document.

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Les boucles diphasiques à pompage thermo-capillaire de type LHP (pour Loop Heat Pipe, en anglais), dont le fonctionnement s’apparente à celui d’un caloduc, permettent un transfert de chaleur particulièrement efficace et entièrement passif entre une source chaude et une source froide. Ce transfert s’effectue au moyen d’un fluide diphasique, mû grâce à la force motrice capillaire générée par un matériau poreux contenu dans l’évaporateur/réservoir de la LHP. Outre son rôle de barrière hydraulique entre les phases liquide et vapeur, ce matériau doit assurer une fonction de barrière thermique afin de favoriser l’évaporation du liquide. L’aptitude du matériau à remplir ses fonctions dépend étroitement de sa microstructure, elle-même liée à la méthode de fabrication. Dès lors, l’objectif de la thèse est d’associer la science des matériaux à celle de la thermique, pour améliorer les procédures de fabrication de structures capillaires existantes ou tester de nouvelles méthodes, et aboutir à des structures dont les caractéristiques sont en adéquation avec celles qui sont recherchées
The capillary pumped loops (CPL) or loop heat pipes (LHP), whom the operating principle is similar to classic heat pipes, enable an efficient heat transfer between a hot source and a cold source without additional energy sources. Indeed, a porous structure provides a capillary force that enables a two-phase fluid to circulate around the loop, transferring the heat from the evaporator to the condenser. The porous structure acts as a hydraulic barrier between the two phases and as a thermal barrier enabling the liquid evaporation. The ability of the capillary structure to fulfil its mission depends on its microstructure, and thus on the manufacturing process. Therefore, the objective of the present thesis is to join the thermal sciences with the material sciences in order to improve the existing manufacturing procedure or even to test new ones. It aims at obtaining capillary structures corresponding to heat transfer applications
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Abdul-Hussain, Najlaa. "Experimental Study on the Engineering Properties of Gelfill." Thèse, Université d'Ottawa / University of Ottawa, 2011. http://hdl.handle.net/10393/19852.

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Gelfill (GF) is made of tailings, water, binder and chemical additives (Fillset, sodium silicate gel). The components of GF are combined and mixed on the surface and transported (by gravity and/or pumping) to the underground mine workings, where the GF can be used for both underground mine support and tailings storage. Thermal (T), hydraulic (H), and mechanical (M) properties are important performance criteria of GF. The understanding of these engineering properties and their evolution with time are still limited due to the fact that GF is a new cemented backfill material. In this thesis, the evolution of the thermal, hydraulic, mechanical, and microstructural properties of small GF samples are determined. Various binder contents of Portland cement type I (PCI) are used. The GF is cured for 3, 7, 28, 90, and 120 days. It is found that the thermal, hydraulic and mechanical properties are time-dependent or affected by the degree of binder hydration index. Furthermore, a relationship is found between the compressive strength and the saturated hydraulic conductivity of the GF samples. The unsaturated hydraulic properties of GF samples have also been investigated. The outcomes show that unsaturated hydraulic conductivity is influenced by the degree of binder hydration index and binder content, especially at low suction ranges. Simple functions are proposed to predict the evolution of air-entry values (AEVs), residual water content, and fitting parameters from the van Genuchten model with the degree of hydration index (α). Furthermore, two columns are built to simulate the coupled thermo-hydro-mechanical (THM) behaviour of GF under drained and undrained conditions. The obtained results from the GF columns are compared with the small samples. It is observed that the mechanical properties, hydraulic properties (suction and water content), and temperature development are strongly coupled. The magnitude of these THM coupling factors is affected by the size of the GF. The findings also show that the mechanical, hydraulic and thermal properties of the GF columns are different from samples cured in plastic moulds.
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"Thermo hydraulic behaviour of unstaturated salt aggregates." Universitat Politècnica de Catalunya, 2007. http://www.tesisenxarxa.net/TDX-0606107-125637/.

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Book chapters on the topic "Thermo-hydraulic behaviour"

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Gerin, G., B. Vullierme, and R. van Weelderen. "Measurement of the Thermo-Hydraulic Behaviour of LHC Dipole Prototypes after Quench." In A Cryogenic Engineering Conference Publication, 811–18. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0373-2_105.

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Lima, A., E. Romero, A. Gens, X. L. Li, and J. Vaunat. "Thermo-Hydraulic Behaviour of Boom Clay Using a Heating Cell: An Experimental Study." In Springer Series in Geomechanics and Geoengineering, 163–68. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-32492-5_19.

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Villar, M. V., R. Gómez-Espina, P. L. Martín, and J. M. Barcala. "Tests in Thermo-Hydraulic Cells to Simulate the Behavior of Engineered Barriers." In Springer Series in Geomechanics and Geoengineering, 137–42. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-32492-5_15.

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Conference papers on the topic "Thermo-hydraulic behaviour"

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Maiti, Abhilash, and B. V. S. S. S. Prasad. "Alternative Heat Sink to Enhance Thermo-Hydraulic Behaviour of an Array of Short Pin Fins." In The 3rd World Congress on Mechanical, Chemical, and Material Engineering. Avestia Publishing, 2017. http://dx.doi.org/10.11159/htff17.121.

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Paulech, Juraj, Justín Murín, Vladimír Kutiš, and Gabriel Gálik. "Thermo-hydraulic behaviour of coolant in nuclear reactor VVER-440 under reactor pool filling conditions." In APPLIED PHYSICS OF CONDENSED MATTER (APCOM 2021). AIP Publishing, 2021. http://dx.doi.org/10.1063/5.0067336.

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Bianchi, Fosco, Roberta Ferri, and Vincent Moreau. "Transient Thermo-Hydraulic Analysis of the Windowless Target System for the Lead Bismuth Eutectic Cooled Accelerator Driven System." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89212.

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The target system, whose function is to supply an external neutron source to the ADS sub-critical core to sustain the neutron chain reaction, is the most critical part of an ADS being subject to severe thermo-mechanical loading and material damage due to accelerator protons and fission neutrons. A windowless option was chosen as reference configuration for the target system of the LBE-cooled ADS within the European PDS-XADS project in order to reduce the material damage and to increase its life. This document deals with the thermo-hydraulic results of the calculations performed with STAR-CD and RELAP5 codes for studying the behaviour of the windowless target system during off-normal operating conditions. It also reports a description of modifications properly implemented in the codes needed for this analysis. The windowless target system shows a satisfactory thermo-hydraulic behaviour for the analysed accidents, except for the loss of both pumps without proton beam shut-off and the beam trips lasting more than one second.
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Adorni, Martina, Alessandro Del Nevo, and Francesco D’Auria. "Methodology for the Analysis of Fuel Behavior During LOCA and RIA for Licensing Purposes." In 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/icone20-power2012-54698.

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Licensing requirements vary by country in terms of their scope, range of applicability and numerical values and may imply the use of system thermal hydraulic computer codes. Depending on the specific event scenario and on the purpose of the analysis, it might be required the availability of calculation methods that are not implemented in the standard system thermal hydraulic codes, as for burst temperature, burst strain and flow blockage calculations. This may imply the use of a dedicated fuel rod thermo-mechanical computer code, which can be coupled with thermal-hydraulic system and neutron kinetic codes to be used for the safety analysis. This paper describes the development and the application of a methodology for the analysis of the Large Break Loss of Coolant Accident (LB-LOCA) scenario in Atucha-2 Nuclear Power Plant (NPP), focusing on the procedure adopted for the use of the fuel rod thermo-mechanical code and its application for the safety analysis (Chapter 15 Final Safety Analysis Report, FSAR). The methodology implies the application of best estimate thermal-hydraulic, neutron physics and fuel pin performance computer codes, with the objective to verify the compliance with the specific acceptance criteria. The fuel pin performance code is applied with the main objective to evaluate the extent of cladding failures during the transient. A strong effort has been performed in order to enhance the fuel behaviour code capabilities and to improve the reliability of the code results.
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Gavriilidis, Ilias, and Spyros A. Karamanos. "Influence of Lined Pipe Fabrication on Liner Wrinkling." In ASME 2019 38th International Conference on Ocean, Offshore and Arctic Engineering. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/omae2019-95743.

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Abstract An economical method to protect offshore pipelines against corrosive ingredients of hydrocarbons is a double-walled (also called “lined” or “bi-metallic”) pipe, in which a thick-walled low-alloy carbon steel (“outer pipe”) is lined internally with a thin layer (“liner pipe”) from a corrosion resistant alloy material. During the deep-water installation, a lined pipe is subjected to severe plastic loading, which may result in detachment of the liner pipe from the outer pipe forming short-wave wrinkles, followed by local buckling. In the current study, alternative lined pipe manufacturing processes are investigated, including elastic, plastic hydraulic and thermo-hydraulic expansion of the outer pipe, for different initial gaps between the two pipes. The problem is solved numerically, accounting for geometric non-linearities, local buckling phenomena and elastic-plastic material behaviour for both the liner and outer pipe. Two types of numerical models are developed, a quasi-two-dimensional model, examining the mechanical bonding between the pipes, and a three-dimensional model, repeating the manufacturing process and investigating its effect on the mechanical behaviour of a lined pipe subjected to monotonic bending. In addition, the influence of initial geometric imperfections on liner pipe buckling is investigated, showing the imperfection sensitivity of the lined pipe bending behaviour, for each fabrication process.
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Gaus, Irina, Klaus Wieczorek, Juan Carlos Mayor, Thomas Trick, Jose´-Luis Garcia` Sin˜eriz, Kristof Schuster, Benoit Garitte, and Uli Kuhlman. "EBS Behaviour Immediately After Repository Closure in a Clay Host Rock: The HE-E Experiment (Mont Terri URL)." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59288.

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The evolution of the engineered barrier system (EBS) of geological repositories for radioactive waste has been the subject of many research programmes during the last decade. The emphasis of the research activities was on the elaboration of a detailed understanding of the complex thermo-hydro-mechanical-chemical processes, which are expected to evolve in the early post closure period in the near field. It is important to understand the coupled THM-C processes and their evolution occurring in the EBS during the early post-closure phase so it can be confirmed that the safety functions will be fulfilled. Especially, it needs to be ensured that interactions during the resaturation phase (heat pulse, gas generation, non-uniform water uptake from the host rock) do not affect the performance of the EBS in terms of its safety-relevant parameters (e.g. swelling pressure, hydraulic conductivity, diffusivity). The 7th Framework PEBS project (Long Term Performance of Engineered Barrier Systems) aims at providing in depth process understanding for constraining the conceptual and parametric uncertainties in the context of long-term safety assessment. As part of the PEBS project a series of laboratory and URL experiments are envisaged to describe the EBS behaviour after repository closure when resaturation is taking place. In this paper the very early post-closure period is targeted when the EBS is subjected to high temperatures and unsaturated conditions with a low but increasing moisture content. So far the detailed thermo-hydraulic behaviour of a bentonite EBS in a clay host rock has not been evaluated at a large scale in response to temperatures of up to 140°C at the canister surface, produced by HLW (and spent fuel), as anticipated in some of the designs considered. Furthermore, earlier THM experiments have shown that upscaling of thermal conductivity and its dependency on water content and/or humidity from the laboratory scale to a field scale needs further attention. This early post-closure thermal behaviour will be elucidated by the HE-E experiment, a 1:2 scale heating experiment setup at the Mont Terri rock laboratory, that started in June 2011. It will characterise in detail the thermal conductivity at a large scale in both pure bentonite as well as a bentonite-sand mixture, and in the Opalinus Clay host rock. The HE-E experiment is especially designed as a model validation experiment at the large scale and a modelling programme was launched in parallel to the different experimental steps. Scoping calculations were run to help the experimental design and prediction exercises taking the final design into account are foreseen. Calibration and prediction/validation will follow making use of the obtained THM dataset. This benchmarking of THM process models and codes should enhance confidence in the predictive capability of the recently developed numerical tools. It is the ultimate aim to be able to extrapolate the key parameters that might influence the fulfilment of the safety functions defined for the long term steady state.
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Sahoo, Benudhar, R. K. Satpathy, and S. K. Panigrahi. "Isothermal Fatigue Behaviour of Two Nickelbase Alloys for Turbine Blades of Fighter Aircraft Engines." In ASME 2013 Gas Turbine India Conference. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/gtindia2013-3682.

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Turbine blades of fighter class aero-engines are subjected to repeated and unsteady throttle excursions during exploitation leading to thermo-mechanical fatigue. Failures of few turbine blades have led to premature withdrawals and major accidents. Hence, there is a need to study the high temperature fatigue behavior of these alloys. This case study deals with the isothermal fatigue behavior at 900°C for two nickel base alloys which are used for manufacturing turbine blades. The materials selected for study are precipitation strengthened wrought nickel base super alloy AP 220BD of Russian origin and western origin nickel base DS cast alloy MAR-M 002. Tensile and low cycle fatigue (LCF) tests were carried out at 900°C. LCF test was carried out at three strain ranges Δεt, i.e., ±0.3%, ±0.5% and ±0.8% using a triangular waveform of frequency 0.33 Hz with the help of MTS 800 servo hydraulic fatigue testing machine. Fractography and metallography have been done on the fracture surface to study the mode of failure and changes in morphology. Both AP220BD and MAR M 002 shows initial cyclic softening followed by cyclic hardening at low strain Δεt, i.e., ±0.3%. Stabilisation of hysteresis loop takes place at strain range Δεt ±0.5% for both the alloys. At Δεt/2 = 0.8%, AP220 BD shows cyclic hardening while MAR M 002 shows cyclic softening. MAR M 002 shows higher degree of hardening compared to that of AP220BD. The reduction in LCF life with increase in strain range is exponential for wrought alloy but for DS cast alloy it is approximately linear. LCF life has been correlated with fatigue damage parameters such as Ostergren energy(σmax Δεp) and plastic strain amplitude Δεp/2. Ostergren energy for MAR-M 002 is found to be significantly less compared to that of AP220BD. The increase in plastic strain range Δεp is significant for wrought alloys. While Ostergren energy is a good indicator of fatigue damage for wrought alloy, plastic strain amplitude Δεp/2 seems to be a better indicator for DS cast alloy. Fractography reveals inter-granular failure with initiation of cracks at at grain boundary / carbides in wrought alloy. DS cast alloy shows cleavage failure with crack initiation at pore cavities in interdendritic spacing.
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Le Brun, N., A. Charogiannis, G. F. Hewitt, and C. N. Markides. "Tackling Coolant Freezing in Generation-IV Molten Salt Reactors." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67984.

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In this study we describe an experimental system designed to simulate the conditions of transient freezing which can occur in abnormal behaviour of molten salt reactors (MSRs). Freezing of coolant is indeed one of the main technical challenges preventing the deployment of MSR. First a novel experimental technique is presented by which it is possible to accurately track the growth of the solidified layer of fluid near a cold surface in an internal flow of liquid. This scenario simulates the possible solidification of a molten salt coolant over a cold wall inside the piping system of the MSR. Specifically, we conducted measurements using water as a simulant for the molten salt, and liquid nitrogen to achieve high heat removal rate at the wall. Particle image velocimetry and planar induced fluorescence were used as diagnostic techniques to track the growth of the solid layer. In addition this study describes a thermo-hydraulic model which has been used to characterise transient freezing in internal flow and compares the said model with the experiments. The numerical simulations were shown to be able to capture qualitatively and quantitatively all the essential processes involved in internal flow transient freezing. Accurate numerical predictive tools such the one presented in this work are essential in simulating the behaviour of MSR under accident conditions.
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Boissiere, Xavier, and Christian Laine. "Water Flow Analysis in a One Eyed Annulus Cavity Subjected to a Perpendicular Flow." In ASME 2005 Pressure Vessels and Piping Conference. ASMEDC, 2005. http://dx.doi.org/10.1115/pvp2005-71672.

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For safety and economic reasons, one of the greatest concerns in modern nuclear power stations is to increase the service life of the steam generator. Enormous work has been undertaken to obtain better knowledge of the mechanical and thermal loads, which are generally overestimated to ensure maximum safety. One of the technical problems is that the reactor is fed with relatively cold (40 °C) water into the hot steam generator. The connection zone, i.e. where the cold water pipe is connected to the steam generator, is protected by an annular cavity inside the feed water nozzle to reduce thermal stresses. We have to identify the thermo-hydraulic behaviour in that zone in order to get more accurate thermal information for the boundary condition in the thermo-mechanical calculations for this connection. No database is available for this configuration model, so we need to qualify the flow before using CFD modeling. Therefore a specific experimental testing bench along with numerical modeling has been developed. The first requirement is that the flow in the annular cavity is representative of the actual one. For this purpose, we used Reynolds and Strouhal similitudes to set up the flow in the model. Attention has been focused on the understanding of the flow in the annular cavity. PIV measurements enable us to have a good understanding of the flow structure. We also present and discuss the results in terms of velocity profiles. The main result is that the flow is unsteady in the cavity and depends on the length and thickness of the annular cavity. Experimental results give us data to validate our numerical approach, which is used to test several configurations.
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Bond, Alex, George Towler, Alan Paulley, and Simon Norris. "Implementation of a Geological Disposal Facility (GDF) in the UK by the NDA Radioactive Waste Management Directorate (RWMD): Coupled Modelling of Gas Generation and Multiphase Flow Between the Co-Located ILW/LLW and HLW/SF Components of a GDF." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16307.

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In June 2008 the UK government published a ‘White Paper’ as part of the “Managing Radioactive Waste Safety” (MRWS) programme to provide a framework for managing higher activity radioactive wastes in the long-term through geological disposal. The White Paper identifies that there are benefits to disposing all of the UK’s higher activity wastes (Low and Intermediate Level Waste (LLW and ILW), High Level Waste (HLW), Spent Fuel (SF), Uranium (U) and Plutonium (Pu)) at the same site, and this is currently the preferred option. It also notes that research will be required to support the detailed design and safety assessment in relation to any potentially detrimental interactions between the different modules. Different disposal system designs and associated Engineered Barrier Systems (EBS) will be required for these different waste types, i.e. ILW/LLW and HLW/SF. If declared as waste U would be disposed as ILW and Pu as HLW/SF. The Geological Disposal Facility (GDF) would therefore comprise two co-located modules (respectively for ILW/LLW and HLW/SF). A study has recently been undertaken by NDA RWMD to identify the key Thermo-Hydro-Mechanical-Chemical (THMC) interactions which might occur during both the operational and post-closure phases in order to assess the potential implications of co-location in a range of host rocks. This paper presents supporting modelling work used to help understand the potential interactions between the modules. A multi-phase flow and coupled gas generation model was used to help investigate the potential groundwater and gas fluxes between the modules, in particular considering the operational phase and resaturation behaviour of the different modules. These early phases are important because gas generation rates and hydraulic gradients will be at their maximum, and the pressure gradients associated with GDF operations will, at least initially, dominate over the background hydraulic gradient. The gas generation and multi-phase flow study considered a mudstone host rock in which gas pressurisation might significantly influence resaturation behaviour, or drive water from one module to the other. The results of the multiphase flow modelling show that although gas generation affects pressure recovery in the ILW/LLW module, the smaller size of the HLW/SF excavations compared with the ILW/LLW excavations, and the operational timings, mean that in general the groundwater pressure gradient in the GDF is from the HLW/SF module (higher pressure) to the ILW module (lower pressure). Transport of solutes from the HLW/SF module towards the ILW module is not expected to result in any deleterious interactions, indicating that hydraulic interactions during the resaturation period are unlikely to pose a fundamental barrier to co-location.
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Reports on the topic "Thermo-hydraulic behaviour"

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TENSILE BEHAVIOUR OF TMCP Q690D HIGH-STRENGTH STRUCTURAL STEEL AT STRAIN RATES FROM 0.00025 TO 760 S-1. The Hong Kong Institute of Steel Construction, March 2022. http://dx.doi.org/10.18057/ijasc.2022.18.1.7.

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The application of Q690D high-strength structural steel (HSSS) has been increasing in engineering structures. The lack of knowledge of the strain rate behaviour limits the application to the extreme loading conditions such as blast and impact loadings. This paper presents a series of tensile tests on the dynamic tensile behaviour of Q690D HSSS produced through the thermo-mechanical control process (TMCP). The stress-strain relationships of TMCP Q690D in the strain rate range of 0.00025 to 760 s-1 were measured by using the universal and servo-hydraulic high speed testing machines. The experimental results verified the sensitivity to strain rate of TMCP Q690D and the dynamic increase factor (DIF) for yield stress is identical to that of QT (Quenched and Tempered) S690 HSSS. However, TMCP Q690D behaves in a much different way in the strain hardening stage. The commonly-used Cowper-Symonds model was calibrated for the DIFs of yield stress and ultimate tensile strength. The Johnson-Cook (J-C) model was modified and a new rate-dependent constitutive model was proposed. The proposed model was validated successfully to predict the true stress-strain relationship, providing better prediction results than the modified J-C model.
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