Academic literature on the topic 'High-temperature tests'

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Journal articles on the topic "High-temperature tests":

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Morgan, V. I. "High-temperature ice creep tests." Cold Regions Science and Technology 19, no. 3 (August 1991): 295–300. http://dx.doi.org/10.1016/0165-232x(91)90044-h.

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Zhmurikov, E. I. "High Temperature Tests for Graphite Materials." Universal Journal of Materials Science 4, no. 5 (September 2016): 113–17. http://dx.doi.org/10.13189/ujms.2016.040502.

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MISAWA, SHIGEO. "Laboratory drilling tests under high temperature and high pressure." Journal of the Japanese Association for Petroleum Technology 50, no. 5 (1985): 372–79. http://dx.doi.org/10.3720/japt.50.372.

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Jakubiak, E. A., and J. S. Matrusz. "High temperature tests of ACSR conductor hardware." IEEE Transactions on Power Delivery 4, no. 1 (1989): 524–31. http://dx.doi.org/10.1109/61.19243.

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Roshchin, M. N. "High-temperature tribological tests of composite materials." IOP Conference Series: Materials Science and Engineering 862 (May 28, 2020): 022008. http://dx.doi.org/10.1088/1757-899x/862/2/022008.

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Wu, Zhuoya, Sai Huen Lo, Kang Hai Tan, and Kai Leung Su. "High Strength Concrete Tests under Elevated Temperature." Athens Journal of Τechnology & Engineering 6, no. 3 (September 1, 2019): 141–62. http://dx.doi.org/10.30958/ajte.6-3-1.

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Xie, W. H., S. H. Meng, L. Ding, H. Jin, G. K. Han, L. B. Wang, Fabrizio Scarpa, and R. Q. Chi. "High velocity impact tests on high temperature carbon-carbon composites." Composites Part B: Engineering 98 (August 2016): 30–38. http://dx.doi.org/10.1016/j.compositesb.2016.05.031.

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Duguay, C., A. Mocellin, Ph Dehaudt, and Gilbert Fantozzi. "High Temperature Compression Tests Performed on Doped Fuels." Key Engineering Materials 132-136 (April 1997): 579–82. http://dx.doi.org/10.4028/www.scientific.net/kem.132-136.579.

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Boitier, G., H. Cubéro, and Jean-Louis Chermant. "Some Recommendations for Long Term High Temperature Tests." Key Engineering Materials 164-165 (July 1998): 309–12. http://dx.doi.org/10.4028/www.scientific.net/kem.164-165.309.

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UENO, Akira, Hidehiro KISHIMOTO, Hiroshi KAWAMOTO, and Sachio URA. "High temperature tensile tests of sintered silicon nitride." Journal of the Society of Materials Science, Japan 39, no. 441 (1990): 716–22. http://dx.doi.org/10.2472/jsms.39.716.

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Dissertations / Theses on the topic "High-temperature tests":

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Shin, Dongyun. "Development of High Temperature Erosion Tunnel and Tests of Advanced Thermal Barrier Coatings." University of Cincinnati / OhioLINK, 2018. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1522415020378523.

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Berny, Myriam. "High-temperature tests for ceramic matrix composites : from full-field regularised measurements to thermomechanical parameter identification." Thesis, université Paris-Saclay, 2020. http://www.theses.fr/2020UPAST028.

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Cette thèse a pour objectif de développer une méthode de mesure de champs par corrélation d’images numériques (CIN) à haute température couplée à des mesures thermiques sur une éprouvette technologique en CMC sollicitée dans des conditions thermiques représentatives d’un environnement moteur et de mettre en place une méthodologie d’identification des propriétés thermiques et thermomécaniques du matériau, en quantifiant à chaque étape de la chaîne les incertitudes associées aux quantités d’intérêt et en les réduisant. Il a pour cela été nécessaire de traiter les défis inhérents à la CIN à chaud, que ce soit au niveau de l’acquisition des images (saturation, perte du contraste) ou de la mesure (artefacts dus à l’effet mirage, aussi appelé "brume de chaleur").Ces travaux ont ainsi donné lieu au développement d’un protocole d’étalonnage d’un banc multi-instrumenté par l’utilisation soit d’une mire in-situ, soit par auto-étalonnage en utilisant l’éprouvette elle-même et son environnement. Les mesures de déplacements 3D surfaciques (approches de stéréocorrélation globales) et les mesures thermiques ont permis de mettre en évidence ce phénomène de brume de chaleur. Des stratégies de régularisation spatiotemporelles des déplacements mesurés ont été proposées et ont permis d’obtenir des résultats satisfaisants (réduction significative des incertitudes de mesure). De même, des approches par réduction de modèles (POD) ont permis de traiter les données thermiques et de quantifier les incertitudes associées aux phénomènes convectifs. Enfin, un algorithme de recalage de modèle éléments finis pondéré sur les données de températures et de déplacements a été implémenté en vue d’identifier un ensemble de propriétés thermiques et thermomécaniques, en tenant compte de la sensibilité de chaque paramètre par rapport aux incertitudes de mesures
The aim of this thesis is firstly to develop procedures of full-field measurements with Digital Image Correlation (DIC), coupled to thermal measurements, suitable for high-temperature experiments on CMC specimens under thermal conditions representative of an engine environment. Secondly, a methodology is proposed for identifying the thermal and thermomechanical properties of the material, quantifying at each stage of the chain the uncertainties associated with the quantities of interest and strategies to reduce them. It was necessary to deal with the challenges due to high temperatures, especially for DIC, either in terms of acquisition (saturation, loss of contrast) or measurement (artefacts due to the mirage effect, also called "heat haze effect").This work has led to the development of a calibration protocol for a multi-instrumented bench using either an in-situ calibration target or by self-calibration using the specimen itself and its environment. 3D surface displacement measurements (with global stereocorrelation approaches) and thermal measurements have made it possible to highlight the heat haze effect phenomenon. Spatiotemporal regularisation strategies of the measured displacements were proposed and allowed satisfactory results to be obtained (significant reduction of measurement uncertainties). Similarly, model reduction approaches (POD) have been used to process thermal data and quantify the uncertainties associated with convective phenomena. Finally, a weighted Finite-Element Model Updating (FEMU) algorithm on both temperature and displacement data was implemented in order to identify a set of thermal and thermomechanical properties, taking into account the sensitivity of each parameter with regard to measurement uncertainties
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Evin, Harold. "Low Cr alloys with an improved high temperature corrosion resistance." Thesis, Dijon, 2010. http://www.theses.fr/2010DIJOS082/document.

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Les aciers ferritiques à faible teneur en chrome tel que le T/P91 sont largement utilisés dans les centrales de productions d’électricité pour leurs bonnes propriétés mécaniques et leur faible coefficient d’expansion thermique. Cependant, la demande croissante en énergie alliée à la nécessité de réduire les émissions de gaz à effet de serre, conduisent à envisager l’augmentation des conditions d’utilisation (température et pression) de ces matériaux. Des études ont montré qu’en modifiant la température de fonctionnement et la pression de vapeur d’eau de 538°C/18.5 MPa à 650°C/30 MPa, le rendement des centrales thermiques progressait d’environ 8%. Se pose alors la question de la tenue à la corrosion à haute température des aciers à 9% de chrome. Au cours de ces travaux, le comportement d’un acier ferritique/ martensitique à 9% de chrome a été étudié à 650°C sous air sec et sous vapeur d’eau de matière isotherme et en conditions de cyclage thermique. La prise de masse des échantillons renseigne sur la cinétique de la réaction d’oxydation et l’adhérence des couches d’oxydes formées. Les produits de corrosion ont été caractérisés par plusieurs techniques d’analyses dans l’optique de clairement identifiés les oxydes en présences et leurs mécanismes de formation. Des oxydes mixtes de fer et de chrome (Cr,Fe)2O3 sont dans un premier temps formés et assurent s’avèrent être temporairement protecteur. Pour des longs temps d’oxydation ou des températures supérieures à 650°C, la magnétite Fe3O4 et l’hématite Fe2O3 sont les principaux oxydes formés, montrant ainsi l’inadéquation des nuances à faible teneur en chrome pour une utilisation dans des conditions aussi drastiques. Dans l’optique d’augmenter la résistance à la corrosion à haute température de cet alliage, diverses solutions ont été envisagées tel que l’aluminisation par cémentation en caisse, les revêtements d’oxydes de terre rare par MOCVD, ou encore l’ajout d’éléments d’addition. Ces solutions ont été également testées à 650°C sous air sec et sous vapeur d’eau
The improvement of high temperature oxidation resistance of low chromium content steels, such as T/P91, is of great interest in regards with their application in thermal power generating plants. Indeed, they possess good creep properties, and low thermal expansion coefficient. Important needs in energy together with environmental issues place power generation plants under constraints which lead to develop high efficiency systems. A usual way to increase the efficiency consists in increasing temperature and pressure parameters of the power generating plant. Studies has shown that the total efficiency of a plant increases by nearly 8 % when changing the steam parameters from 538°C/18.5 MPa to 650°C/30 MPa. Then, the problem of corrosion resistance of 9% chromium steel in those conditions is asked. In this work, the behavior of a ferritic / martensitic 9% chromium steel has been studied at 650°C in dry air and in water vapor containing environment in both isothermal and thermal cyclic conditions. The weight gain of samples provides information on the kinetics of the oxidation reaction and the adhesion of formed oxide scale. Corrosion products were characterized by several analytical techniques in order to identify oxides with accuracy and to understand their formation mechanisms. Mixed iron and chromium oxides (Cr, Fe) 2O3 are initially formed and provide temporary protection to the substrate. For long time exposure or temperatures above 650°C, magnetite, Fe3O4 and hematite Fe2O3 are the main oxides formed, highlighting the fact that low chromium steel are inappropriate for applications in such drastic conditions. In order to increase the high temperature corrosion resistance of this alloy, various solutions have been proposed as aluminizing by pack cementation, reactive element oxides coatings of by MOCVD, or addition of alloying elements in the steel composition. These solutions were then tested at 650 ° C in dry air and in water vapor environments
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Willschütz, H. G., and E. Altstadt. "Generation of a High Temperature Material Data Base and its Application to Creep Tests with French or German RPV-steel." Forschungszentrum Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-29413.

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Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible failure mode of the reactor pressure vessel (RPV) and its failure time has to be investigated for a determination of the loadings on the containment. Numerous experiments have been performed accompanied with material properties evaluation, theoretical, and numerical work /REM 1993/, /THF 1997/, /CHU 1999/. For pre- and post-test calculations of Lower Head Failure experiments like OLHF or FOREVER it is necessary to model creep and plasticity processes. Therefore a Fi-nite Element Model is developed at the FZR using a numerical approach which avoids the use of a single creep law employing constants derived from the data for a limited stress and temperature range. Instead of this a numerical creep data base (CDB) is developed where the creep strain rate is evaluated in dependence on the current total strain, temperature and equivalent stress. A main task for this approach is the generation and validation of the CDB. Additionally the implementation of all relevant temperature dependent material properties has been performed. For an evaluation of the failure times a damage model according to an approach of Lemaitre is applied. The validation of the numerical model is performed by the simulation of and com-parison with experiments. This is done in 3 levels: starting with the simulation of sin-gle uniaxial creep tests, which is considered as a 1D-problem. In the next level so called "tube-failure-experiments" are modeled: the RUPTHER-14 and the "MPA-Meppen"-experiment. These experiments are considered as 2D-problems. Finally the numerical model is applied to scaled 3D-experiments, where the lower head of a PWR is represented in its hemispherical shape, like in the FOREVER-experiments. This report deals with the 1D- and 2D-simulations. An interesting question to be solved in this frame is the comparability of the French 16MND5 and the German 20MnMoNi55 RPV-steels, which are chemically nearly identical. Since these 2 steels show a similar behavior, it should be allowed on a lim-ited scale to transfer experimental and numerical data from one to the other.
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Willschütz, H. G., and E. Altstadt. "Generation of a High Temperature Material Data Base and its Application to Creep Tests with French or German RPV-steel." Forschungszentrum Rossendorf, 2002. https://hzdr.qucosa.de/id/qucosa%3A21768.

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Considering the hypothetical core melt down scenario for a light water reactor (LWR) a possible failure mode of the reactor pressure vessel (RPV) and its failure time has to be investigated for a determination of the loadings on the containment. Numerous experiments have been performed accompanied with material properties evaluation, theoretical, and numerical work /REM 1993/, /THF 1997/, /CHU 1999/. For pre- and post-test calculations of Lower Head Failure experiments like OLHF or FOREVER it is necessary to model creep and plasticity processes. Therefore a Fi-nite Element Model is developed at the FZR using a numerical approach which avoids the use of a single creep law employing constants derived from the data for a limited stress and temperature range. Instead of this a numerical creep data base (CDB) is developed where the creep strain rate is evaluated in dependence on the current total strain, temperature and equivalent stress. A main task for this approach is the generation and validation of the CDB. Additionally the implementation of all relevant temperature dependent material properties has been performed. For an evaluation of the failure times a damage model according to an approach of Lemaitre is applied. The validation of the numerical model is performed by the simulation of and com-parison with experiments. This is done in 3 levels: starting with the simulation of sin-gle uniaxial creep tests, which is considered as a 1D-problem. In the next level so called "tube-failure-experiments" are modeled: the RUPTHER-14 and the "MPA-Meppen"-experiment. These experiments are considered as 2D-problems. Finally the numerical model is applied to scaled 3D-experiments, where the lower head of a PWR is represented in its hemispherical shape, like in the FOREVER-experiments. This report deals with the 1D- and 2D-simulations. An interesting question to be solved in this frame is the comparability of the French 16MND5 and the German 20MnMoNi55 RPV-steels, which are chemically nearly identical. Since these 2 steels show a similar behavior, it should be allowed on a lim-ited scale to transfer experimental and numerical data from one to the other.
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Rahmanian, Ima. "Thermal and mechanical properties of gypsum boards and their influences on fire resistance of gypsum board based systems." Thesis, University of Manchester, 2011. https://www.research.manchester.ac.uk/portal/en/theses/thermal-and-mechanical-properties-of-gypsum-boards-and-their-influences-on-fire-resistance-of-gypsum-board-based-systems(d8eb4bf5-706a-4264-911f-9584ebfbbc83).html.

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Gypsum board assemblies are now widely used in buildings, as fire resistant walls or ceilings, to provide passive fire protection. The fire resistance of such systems is fundamentally due to the desirable thermal properties of gypsum. Yet there is wide variability in reported values of thermal properties of gypsum at high temperatures and a lack of understanding of its integrity in fire. To evaluate the fire protection performance of gypsum board assemblies, it is essential to quantify its thermal properties and obtain information on its mechanical properties at high temperatures. Gypsum boards shrink and crack at high temperatures, and this leads to collapse of parts of the gypsum boards in fire. Fall-off of gypsum in fire affects the fire resistance of the assembly considerably, and cannot be overlooked when evaluating the fire resistance of gypsum board assemblies. The current research proposes a model to define the temperature-dependent thermal properties of gypsum boards at high temperatures. Thermal conductivity of gypsum is considered as the most influential parameter in conduction of heat through gypsum, and a hybrid numerical-experimental method is presented for extracting thermal conductivity of various gypsum board products at elevated temperatures. This method incorporates a validated one-dimensional Finite Difference heat conduction program and high temperature test results on small samples of gypsum boards. Moreover, high temperature mechanical tests have been performed on different gypsum board products; thermal shrinkage, strength and stress-strain relationships of gypsum products at elevated temperatures are extracted for use in numerical mechanical analysis. To simulate the structural performance of gypsum boards in fire, a two-dimensional Finite Element model has been developed in ABAQUS. This model successfully predicts the complete opening of a through-thickness crack in gypsum, and is validated against medium-scale fire tests designed and conducted as part of this research. Gypsum fall-off in fire is a complex phenomenon; however, it is believed that delaying the formation of through-thickness cracking will delay falling off of gypsum in fire, and hence improve the fire resistance of gypsum board assemblies. Finally, a study has been performed on the effects of various detailing parameters in gypsum board wall assemblies, and recommendations are offered for improving the fire resistance of such systems.
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Guillou, Sebastien. "Etude du comportement d'un alliage chromino-formeur comme matériau d'interconnecteur pour l'Electrolyse à Haute Température." Thesis, Dijon, 2011. http://www.theses.fr/2011DIJOS082/document.

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Dans les systèmes d’Electrolyse Haute Température (EHT), le matériau choisi comme interconnecteur doit avoir une bonne résistance à la corrosion sous air et sous mélange H2/H2O à 800 °C, et maintenir une bonne conductivité sur de longues durées. Dans ce cadre, l’objectif de ce travail était, d’une part, d’évaluer un alliage ferritique commercial (l’alliage K41X) comme matériau d’interconnecteur pour l’application EHT. Dans ce but, ont été mis en place des essais d’oxydation en four et en thermoblance pour accéder aux cinétiques d’oxydation, et des mesures de résistivité pour évaluer le paramètre ASR (Area Specific Resistance) à 800°C. D’autre part, l’étude a permis d’apporter des éléments de compréhension plus fondamentaux sur les mécanismes d’oxydation des alliages chromino-formeurs, en particulier sous mélange H2-H2O, par le biais d’essais et de caractérisations spécifiques (Photoélectrochimie, traçage isotopique, essais de longues durées). Cette double stratégie est également appliquée pour l’étude d’une solution de revêtement (obtenu à l’aide de la MOCVD) basée sur l’oxyde pérovskite LaCrO3 qui présente des propriétés de conductivité élevée particulièrement intéressante en vue de l’application EHT. Ainsi, cette étude amène également des éléments de compréhension sur le rôle du lanthane comme élément réactif dont l’effet est souvent discuté dans la littérature. Pour les deux milieux, à 800°C, la couche d’oxyde formée est une couche duplexe Cr2O3/(Mn,Cr)3O4 , recouverte dans le cas du mélange H2-H2O par une fine couche d’oxyde spinelle Mn2TiO4 . Sous air, le mécanisme de croissance déterminé ici est cationique, en accord avec la littérature. La présence d’un revêtement LaCrO3 ne modifie pas ce mécanisme mais ralentit la cinétique de croissance de la couche sur les premières centaines d’heure. De plus, le revêtement améliore l’adhérence et la conductivité de la couche d’oxyde. Sous mélange H2-H2O, le mécanisme de croissance se révèle anionique. La présence de revêtement ralentit la cinétique d’oxydation. Bien que .d’épaisseurs similaires, les couches d’oxyde présentent sous air une résistivité d’un ordre de grandeur inférieure à celle mesurée sous H2-H2O. Il est mis en évidence que la forte résistivité de l’alliage en milieu H2-H2O est liée à la présence de protons issus de la vapeur d’eau présents dans la couche d’oxyde. Le revêtement ne permet néanmoins pas d améliorer la conductivité sous H2-H2O
In High Temperature Vapor Electrolysis (HTVE) system, the materials chosen for the interconnectors should have a good corrosion behaviour in air and in H2-H2O mixtures at 800°C, and keep a high electronic conductivity over long durations as well. In this context, the first goal of this study was to evaluate a commercial ferritic alloy (the K41X alloy) as interconnect for HTVE application. Oxidation tests in furnace and in microbalance have therefore been carried out in order to determine oxidation kinetics. Meanwhile, the Area Specific Resistance (ASR) was evaluated by Contact Resistance measurements performed at 800°C. The second objective was to improve our comprehension of chromia-forming alloys oxidation mechanism, in particular in H2/H2O mixtures. For that purpose, some specific tests have been conducted: tracer experiments, coupled with the characterization of the oxide scale by PEC (PhotoElectroChemistry). This approach has also been applied to the study of a LaCrO3 perovskite oxide coating on the K41X alloy. This phase is indeed of high interest for HTVE applications due to its high conductivity properties. This latter study leads to further understanding on the role of lanthanum as reactive element, which effect is still under discussion in literature.In both media at 800°C, the scale is composed of a Cr2O3/(Mn,Cr)3O4 duplex scale, covered in the case of H2-H2O mixture by a thin scale made of Mn2TiO4 spinel. In air, the growth mechanism is found to be cationic, in agreement with literature. The LaCrO3 coating does not modify the direction of scale growth but lowers the growth kinetics during the first hundreds hours. Moreover, with the coating, the scale adherence is favored and the conductivity appears to be slightly higher. In the H2-H2O mixture, the growth mechanism is found to be anionic. The LaCrO3 coating diminishes the oxidation kinetics. Although the scale thickness is about the same in both media, the ASR parameter is one order of magnitude higher in H2/H2O than in air. Specific contact resistance tests show that the higher resistivity in the H2/H2O mixture is closely linked to the presence of protons in the scale. Moreover, tracer experiments show that these protons come from the water molecule dissociation, and not from the H2 molecule. In H2/H2O, the LaCrO3 coating does not increase the conductivity
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Ceccon, Lorenzo. "Effetto dell'esposizione ad alta temperatura su microstruttura e proprietà meccaniche di ghise sferoidali." Master's thesis, Alma Mater Studiorum - Università di Bologna, 2017.

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Lo scopo della presente ricerca è stato valutare l’effetto dell’esposizione ad alta temperatura su microstruttura e proprietà meccaniche di quattro ghise sferoidali prodotte dalle Fonderie Zanardi: ADI 1050 (ghisa duttile austemperata), IDI 800 (ghisa perlitica isotermica), GJS/800-2 (ghisa sferoidale perlitica) e GJS/400-18 (ghisa sferoidale ferritica). Lo studio ha previsto il degrado in temperatura dei quattro materiali, l’analisi delle proprietà meccaniche statiche dopo degrado termico mediante prove di durezza Brinell, analisi microstrutturali, XRD, prove di trazione sia a freddo che alla temperatura di degrado. Per quanto concerne le prove di durezza, è emerso che superata la temperatura di 500 °C la durezza dei materiali ADI 1050 e IDI 800 cala significativamente, la durezza della GJS/800-2 risulta stabile fino a 550 °C, mentre per la GJS/400-18 la durezza rimane pressoché costante fino a 600 °C. Le analisi microstrutturali hanno mostrato che nell’ADI 1050, IDI 800 e GJS/800-2 la matrice si trasforma sino a diventare quasi completamente ferritica a temperatura di degrado di 600 °C mantenuta per 120 ore. Nella ghisa sferoidale ferritica invece non vi sono mutamenti significativi nella microstruttura dopo degrado. Le prove di trazione svolte sulla lega ADI 1050 hanno evidenziato una diminuzione di circa 50-60 % della tensione di rottura e quella di snervamento nei provini degradati e trazionati a 500°C rispetto ai provini degradati trazionati a temperatura ambiente, ed una diminuzione di circa 20 % della tensione di rottura e quella di snervamento nei provini degradati rispetto ai provini non degradati trazionati a temperatura ambiente. Le prove di trazione a temperatura ambiente su ghisa sferoidale perlitica degradata hanno mostrato un calo delle proprietà resistenziali di circa il 6% nei provini degradati a 240 ore mentre nella ghisa IDI 800 degradata si è notato un calo di circa il 10% delle proprietà resistenziali già nei provini degradati a 72 ore
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Xian, Wei. "Development and test of a high temperature superconducting permanent magnet synchronous motor." Thesis, University of Cambridge, 2011. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.609701.

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Mateus, Freire Lucie. "Évolutions microstructurales et comportement en fluage à haute température d'un acier inoxydable austénitique." Thesis, Paris Sciences et Lettres (ComUE), 2018. http://www.theses.fr/2018PSLEM016/document.

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La thèse est inscrite au sein du projet ASTRID, qui est un démonstrateur technologique pour les réacteurs de quatrième génération (Gen-IV). Le premier matériau choisi pour constituer les gaines de cœur est un acier inoxydable austénitique stabilisé au titane (type 15Cr-15Ni Ti). L’écrouissage à froid des gaines permet la précipitation de nano-carbures de titane en service sur les dislocations, retardant ainsi les phénomènes de restauration par effet d’épinglage. En conditions accidentelles (T > 650°C), et plus particulièrement dans le cas d’une perte de réfrigérant primaire, le comportement en fluage de ces gaines est très mal connu. L’objectif des travaux de thèse est donc de déterminer les mécanismes de déformation et de rupture en fluage, entre 650°C et 950°C, de cet acier à l’état non irradié.Dans un premier temps, les microstructures d’échantillons après différents recuits ont été comparées afin d’étudier l’influence de la température sur les évolutions métallurgiques. L’étude de la précipitation et des cinétiques de restauration et de recristallisation, ont permis de dresser les évolutions microstructurales sans charge appliquée.En plus d’étudier le comportement en fluage uniaxial de l’acier à haute température, les caractérisations des éprouvettes après essais ont permis de déterminer les évolutions microstructurales au cours et après essais de fluage (contributions simultanées de la température et de la contrainte). La comparaison avec les microstructures obtenues après recuits a mis en évidence une accélération de la cinétique de recristallisation sous charge, rendant l’effet de la contrainte sur ces évolutions non négligeable.Après fluage sous air aux plus basses températures (650°C et 750°C), les fractographies présentent une rupture globalement transgranulaire avec certaines zones intergranulaires. Après fluage sous vide secondaire à plus hautes températures (850°C et 950°C), un fort amincissement des éprouvettes et une striction quasiment complète dans l’épaisseur ont été observés. Ce fort amincissement se traduit par un alignement de cupules, caractéristique de ruptures 100% ductiles à très haute température
The ASTRID project aims at designing a fast-reactor prototype for the 4th generation of nuclear power plants. The material to be used for fuel cladding is a cold-worked austenitic stainless steel stabilized with titanium (15Cr-15Ni Ti type) and optimized in minor elements. This material was developed to limit recovery and irradiation-induced swelling and to improve microstructural stability and mechanical properties in normal operating conditions. In case of incidental situations (irradiation temperature > 650°C), the cladding might rapidly reach higher temperatures up to 950°C where its stability could be affected. The present work aims at improving knowledge and understanding of the microstructural evolution and creep behaviour of this steel at these temperatures (650°C-950°C).Microstructural characterizations of thermally-aged samples have been performed in order to study the effect of temperature on metallurgical evolutions (precipitation, recovery and recrystallization). A phenomenological model including recovery and recrystallization processes was set up to reproduce hardness measurements versus ageing time and temperatures.Isothermal creep tests up to 950°C under a wide range of stress levels allowed investigation of viscoplastic flow, microstructural evolution under stress and damage/failure processes. In order to evaluate the effect of high-temperature loading, microstructural characteristics of stress-free thermally-aged samples were compared with post-mortem examinations of creep specimens.At 650°C and 750°C the value of stress exponent is higher than 7. The main deformation mechanism during creep test is power-low creep, which is consistent with the results found in the literature.Beyond 850°C, the increase in dislocation mobility promotes recovery and recrystallization processes. As a consequence, a competition between work hardening due to viscoplastic deformation and softening due to dynamic recovery takes place. At 950°C, viscoplastic flow is strongly affected by recrystallization during creep test, especially in the tertiary stage. The comparison between microstructures of crept specimens and stress-free, thermally-aged samples leads to the conclusion that the recrystallization kinetics is accelerated by application of a mechanical loading.As for the fracture behaviour, creep tests under air environment at lower temperatures (650°C-750°C), led to predominating ductile fracture but some intergranular zones were observed on fracture surfaces. Creep tests under high vacuum at higher temperatures (850°C-950°C) lead to a high fracture elongation with a reduction of area up to 100%

Books on the topic "High-temperature tests":

1

Wilkinson, C. High temperature cyclic behaviour of aerospace materials: room temperature validation tests of Ti-6Al-4V. Neuilly sur Seine, France: AGARD, 1994.

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Mines, United States Bureau of. High-temperature cyanide leaching of platinum-group metals from automobile catalysts--laboratory tests. Pittsburgh, PA: U.S. Dept. of the Interior, Bureau of Mines, 1991.

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C, Moore Thomas. Recommended strain gage application procedures for various Langley Research Center balances and test articles. Hampton, Va: National Aeronautics and Space Administration, Langley Research Center, 1997.

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DellaCorte, Christopher. Tribological properties of PM212: A high-temperature, self-lubricating, powder metallurgy composite. Cleveland, Ohio: Lewis Research Center, 1989.

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Wilkinson, C. Structures and Materials Panel Working Group 26 on High temperature cyclic behaviour of aerospace materials: Room temperature validation tests of Ti-6AI-4V. Neuilly sur Seine: Agard, 1994.

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E, Smith James. High temperature furnace modeling and performance verifications: Final report, NAG8-708-final. Huntsville, Ala: Dept. of Chemical and Materials Engineering, College of Engineering, University of Alabama in Huntsville, 1992.

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undifferentiated, J. H. Miller. Use of high-T[subscript c] superconducting magnetic sensors for nondestructive evaluation of subsurface defects: Final report. [Washington, DC: National Aeronautics and Space Administration, 1998.

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Perdomo, Andrés Bertrand. Absorption of water and lubricating oils into porous nylon. El Segundo, Calif: The Aerospace Corporation, 1995.

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Whittenberger, J. Daniel. Elevated temperature creep properties of NiAl cryomilled with and without Y₂O₃. [Washington, D.C: National Aeronautics and Space Administration, 1995.

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E, Smith James. High temperature furnace modeling and performance verifications: Semi-annual progress report, NAG8-708-1. Huntsville, Ala: Dept. of Mechanical Engineering, College of Engineering, University of Alabama in Huntsville, 1988.

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Book chapters on the topic "High-temperature tests":

1

Archer, T., P. Beauchêne, M. Berny, and F. Hild. "Multi-instrumentation of Very High Temperature Tests." In Residual Stress, Thermomechanics & Infrared Imaging, Hybrid Techniques and Inverse Problems, Volume 7, 73–76. Cham: Springer International Publishing, 2018. http://dx.doi.org/10.1007/978-3-319-95074-7_14.

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Kitagawa, Masaki, and Koji Yamaguchi. "Japanese Activities in VAMAS Low Cycle Fatigue Round Robin Tests." In Harmonisation of Testing Practice for High Temperature Materials, 241–54. Dordrecht: Springer Netherlands, 1992. http://dx.doi.org/10.1007/978-94-011-2888-9_11.

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Kapitulnik, A. "Tests for Nonreciprocal Optical Effects in High-Temperature Superconductors." In Springer Series in Solid-State Sciences, 256–62. Berlin, Heidelberg: Springer Berlin Heidelberg, 1993. http://dx.doi.org/10.1007/978-3-642-84865-0_42.

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Galerie, Alain, M. Dupeux, Yves Wouters, and F. Toscan. "Quantitative Adhesion Energy Values of Chromia-Rich Thermal Oxides on Stainless Steels Determined by Blister and Tensile Tests." In High-Temperature Oxidation and Corrosion 2005, 441–50. Stafa: Trans Tech Publications Ltd., 2006. http://dx.doi.org/10.4028/0-87849-409-x.441.

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Yuan, Weijia. "Coil Tests and Applications for SMES." In Second-Generation High-Temperature Superconducting Coils and Their Applications for Energy Storage, 105–38. London: Springer London, 2011. http://dx.doi.org/10.1007/978-0-85729-742-6_6.

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Thien, Volker. "Selection and Qualification Tests of High Temperature Materials by Special Microanalytical Methods." In Progress in Materials Analysis, 229–61. Vienna: Springer Vienna, 1985. http://dx.doi.org/10.1007/978-3-7091-8840-8_17.

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Minami, M., S. Nagaya, N. Hirano, H. Kawashima, and H. Sekimoto. "Tests on Small Sized Rotary Model of Flywheel with High Temperature Superconducting Magnetic Bearings." In Advances in Superconductivity VIII, 1365–68. Tokyo: Springer Japan, 1996. http://dx.doi.org/10.1007/978-4-431-66871-8_307.

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Yan, Yun Qi, L. Zhou, and Chang Qi Chen. "Flow Stress and Microstructural Evolution of AM50 Alloy during Upsetting Forging Tests at High Temperature." In Materials Science Forum, 815–18. Stafa: Trans Tech Publications Ltd., 2005. http://dx.doi.org/10.4028/0-87849-968-7.815.

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L’Homme, G. A., J. P. Pirard, and P. Ledent. "Oxy-Reactivity of Coal at Low Temperature and High Pressure During Great Depth Underground Gasification Tests." In Fundamental Issues in Control of Carbon Gasification Reactivity, 107–29. Dordrecht: Springer Netherlands, 1991. http://dx.doi.org/10.1007/978-94-011-3310-4_6.

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Hofstötter, Peter. "Laboratory Tests on Encapsulated High Temperature Strain Gages SG 425 for Measurements up to 530°C." In Experimental Stress Analysis, 579–88. Dordrecht: Springer Netherlands, 1986. http://dx.doi.org/10.1007/978-94-009-4416-9_63.

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Conference papers on the topic "High-temperature tests":

1

Lin, Edward, and James Stultz. "Cassini MLI blankets high-temperature exposure tests." In 33rd Aerospace Sciences Meeting and Exhibit. Reston, Virigina: American Institute of Aeronautics and Astronautics, 1995. http://dx.doi.org/10.2514/6.1995-633.

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Anderson, William G. "High Temperature Water Heat Pipe Life Tests." In SPACE TECH.& APPLIC.INT.FORUM-STAIF 2006: 10th Conf Thermophys Applic Microgravity; 23rd Symp Space Nucl Pwr & Propulsion; 4th Conf Human/Robotic Tech & Nat'l Vision for Space Explor.; 4th Symp Space Coloniz.; 3rd Symp on New Frontiers & Future Concepts. AIP, 2006. http://dx.doi.org/10.1063/1.2169185.

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Baxi, C. B., N. G. Kodochigov, S. E. Belov, and M. N. Borovkov. "Rotor Scale Model Tests for Power Conversion Unit of GT-MHR." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58015.

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A power-generating unit with the high-temperature helium reactor (GT-MHR) has a turbomachine (TM) that is intended for both conversion of coolant thermal energy into electric power in the direct gas-turbine cycle, and provision of helium circulation in the primary circuit. The vertically oriented TM is placed in the central area of the power conversion unit (PCU). TM consists of a turbocompressor (TC) and a generator. Their rotors are joined with a diaphragm coupling and supported by electro-magnetic bearings (EMB). The complexity and novelty of the task of the full electromagnetic suspension system development requires thorough stepwise experimental work, from small-scale physical models to full-scale specimen. On this purpose, the following is planned within the framework of the GT-MHR Project: investigations of the “flexible” rotor small-scale mockup with electro-magnetic bearings (“Minimockup” test facility); tests of the radial EMB; tests of the position sensors; tests of the TM rotor scale model; tests of the TM catcher bearings (CB) friction pairs; tests of the CB mockups; tests of EMB and CB pilot samples and investigation of the full-scale electromagnetic suspension system as a part of full-scale turbocompressor tests. The rotor scale model (RSM) tests aim at investigation of dynamics of rotor supported by electromagnetic bearings to validate GT-MHR turbomachine serviceability. Like the full-scale turbomachine rotor, the RSM consist of two parts: the generator rotor model and the turbocompressor rotor model that are joined with a coupling. Both flexible and rigid coupling options are tested. Each rotor is supported by one axial and two radial EMBs. The rotor is arranged vertically. The RSM rotor length is 10.54 m, and mass is 1171 kg. The designs of physical model elements, namely of the turbine, compressors, generator and exciter, are simplified and performed with account of rigid characteristics, which are identical to those of the full-scale turbomachine elements.
4

Barnes, Charles M., W. C. Richardson, DeWayne Husser, and Matthias Ebner. "Fabrication Process and Product Quality Improvements in Advanced Gas Reactor UCO Kernels." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58039.

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A major element of the Next Generation Nuclear Plant (NGNP)/Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is developing fuel fabrication processes to produce high quality uranium-containing fuel kernels, TRISO-coated particles and fuel compacts needed for planned irradiation tests. The goals of the program also include developing the fabrication technology to mass produce this fuel at low cost. Kernels for the first AGR test, AGR-1, consisted of uranium oxycarbide (UCO) microspheres that were produced by an internal gelation process followed by high temperature steps to convert the UO3 + C “green” microspheres to UO2 + UCx. The high temperature steps also densified the kernels. Babcock and Wilcox (B&W) fabricated UCO kernels in their Lynchburg facility for the AGR-1 irradiation experiment, which went into the Advanced Test Reactor (ATR) at Idaho National Laboratory in December 2006. An evaluation of the kernel process prior and after these kernels were produced led to several recommendations to improve the fabrication process. These recommendations included testing alternative methods of dispersing carbon during broth preparation, evaluating the method of broth mixing, optimizing the broth chemistry, optimizing sintering conditions, and demonstrating fabrication of larger diameter UCO kernels needed for the second AGR irradiation test, AGR-2. Based on these recommendations and requirements, a test program was defined and performed. Certain portions of the test program were performed by Oak Ridge National Laboratory (ORNL), while tests at larger scale were performed by B&W. The tests at B&W have demonstrated improvements in both kernel properties and process operation. Changes in the form of carbon black used and the method of mixing the carbon prior to forming kernels led to improvements in the phase distribution in the sintered kernels, greater consistency in kernel properties, a reduction in forming run time, and simplifications to the forming process. Process parameter variation tests in both forming and sintering steps led to an increased understanding of the acceptable ranges for process parameters and additional reduction in required operating times. Another result of this test program was to double the kernel production rate. Following the development tests, approximately 40 kg of natural uranium UCO kernels have been produced for use in coater scale up tests, and approximately 10 kg of low enriched uranium UCO kernels for use in the AGR-2 experiment.
5

Barnes, Charles M., Douglas W. Marshall, John Hunn, Bruce L. Tomlin, and Joe T. Keeley. "Results of Tests to Demonstrate a Six-Inch Diameter Coater for Production of TRISO-Coated Particles for Advanced Gas Reactor Experiments." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58074.

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The Next Generation Nuclear Plant (NGNP)/Advanced Gas Reactor (AGR) Fuel Development and Qualification Program includes a series of irradiation experiments in Idaho National Laboratory’s (INL’s) Advanced Test Reactor. TRISO-coated particles for the first AGR experiment, AGR-1, were produced at Oak Ridge National Laboratory (ORNL) in a two-inch diameter coater. A requirement of the NGNP/AGR Program is to produce coated particles for later experiments in coaters more representative of industrial scale. Toward this end, tests have been performed by Babcock and Wilcox (B&W) in a six-inch diameter coater. These tests are expected to lead to successful fabrication of particles for the second AGR experiment, AGR-2. While a thorough study of how coating parameters affect particle properties was not the goal of these tests, the test data obtained provides insight into process parameter/coated particle property relationships. Most relationships for the six-inch diameter coater followed trends found with the ORNL two-inch coater, in spite of differences in coater design and bed hydrodynamics. For example the key coating parameters affecting pyrocarbon anisotropy were coater temperature, coating gas fraction, total gas flow rate and kernel charge size. Anisotropy of the outer pyrolytic carbon (OPyC) layer also strongly correlates with coater differential pressure. In an effort to reduce the total particle fabrication run time, silicon carbide (SiC) was deposited with methyltrichlorosilane (MTS) concentrations up to 3 mol %. Using only hydrogen as the fluidizing gas, the high concentration MTS tests resulted in particles with lower than desired SiC densities. However when hydrogen was partially replaced with argon, high SiC densities were achieved with the high MTS gas fraction.
6

Stoots, Carl M., James E. O’Brien, J. Stephen Herring, Keith G. Condie, and Joseph J. Hartvigsen. "Idaho National Laboratory Experimental Research in High Temperature Electrolysis for Hydrogen and Syngas Production." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58086.

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The Idaho National Laboratory (Idaho Falls, Idaho, USA), in collaboration with Ceramatec, Inc. (Salt Lake City, Utah, USA), is actively researching the application of solid oxide fuel cell technology as electrolyzers for large scale hydrogen and syngas production. This technology relies upon electricity and high temperature heat to chemically reduce a steam or steam / CO2 feedstock. Single button cell tests, multi-cell stack, as well as multi-stack testing has been conducted. Stack testing used 10 × 10 cm cells (8 × 8 cm active area) supplied by Ceramatec and ranged from 10 cell short stacks to 240 cell modules. Tests were conducted either in a bench-scale test apparatus or in a newly developed 5 kW Integrated Laboratory Scale (ILS) test facility. Gas composition, operating voltage, and operating temperature were varied during testing. The tests were heavily instrumented, and outlet gas compositions were monitored with a gas chromatograph. The ILS facility is currently being expanded to ∼15 kW testing capacity (H2 production rate based upon lower heating value).
7

Wang, J. C., and M. A. Sublette. "High Temperature Liquid Lubricant Development Part I: Engine Tests." In International Fuels & Lubricants Meeting & Exposition. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 1993. http://dx.doi.org/10.4271/932842.

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van der Merwe, Hanno, and Dirk Olivier. "Modelling Silver: Evaluation of German Experience." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58105.

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For direct cycle gas cooled high temperature reactor designs, operating conditions may be limited as a result of excessive maintenance dose rates caused by the Ag-110m source term on the turbine. It is therefore important to accurately predict silver release from fuel during reactor operation. Traditionally diffusion models were used to derive transport parameters from limited irradiation testing of fuel materials and components. Best estimates for all applicable German fuel irradiation tests with defendable uncertainty ranges were never derived. However, diffusion theory and current parameters cannot account for all irradiation and heat-up test results, and for some tests, it appears unacceptably conservative. Other transport mechanisms have been suggested, and alternative calculation models are being considered. In this paper the applicable German irradiation test results are evaluated with a classic diffusion model as well as an alternative model called the Molecular Vapour transport Release (MVR) model. New transport models and parameters for silver in fuel materials are suggested and compared.
9

Calvillo, P. R., N. Lasa García, and Y. Houbaert. "High Temperature Straining Behaviour Of High FeSi Electrical Steel By Torsion Tests." In 10TH ESAFORM CONFERENCE ON MATERIAL FORMING. AIP, 2007. http://dx.doi.org/10.1063/1.2729554.

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Balls, Vondell J., David S. Duncan, and Stephanie L. Austad. "The Component Test Facility: A National User Facility for Testing of High Temperature Gas-Cooled Reactor (HTGR) Components and Systems." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58250.

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The Next Generation Nuclear Plant (NGNP) and other High-Temperature Gas-cooled Reactor (HTGR) Projects require research, development, design, construction, and operation of a nuclear plant intended for both high-efficiency electricity production and high-temperature industrial applications, including hydrogen production. During the life cycle stages of an HTGR, plant systems, structures and components (SSCs) will be developed to support this reactor technology. To mitigate technical, schedule, and project risk associated with development of these SSCs, a large-scale test facility is required to support design verification and qualification prior to operational implementation. As a full-scale helium test facility, the Component Test facility (CTF) will provide prototype testing and qualification of heat transfer system components (e.g., Intermediate Heat Exchanger, valves, hot gas ducts), reactor internals, and hydrogen generation processing. It will perform confirmation tests for large-scale effects, validate component performance requirements, perform transient effects tests, and provide production demonstration of hydrogen and other high-temperature applications. Sponsored wholly or in part by the U.S. Department of Energy, the CTF will support NGNP and will also act as a National User Facility to support worldwide development of High-Temperature Gas-cooled Reactor technologies.

Reports on the topic "High-temperature tests":

1

John D. Bess, Nozomu Fujimoto, James W. Sterbentz, Luka Snoj, and Atsushi Zukeran. Evaluation of the Start-Up Core Physics Tests at Japan's High Temperature Engineering Test Reactor (Annular Core Loadings). Office of Scientific and Technical Information (OSTI), March 2010. http://dx.doi.org/10.2172/983333.

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John D. Bess, Nozomu Fujimoto, Barbara H. Dolphin, Luka Snoj, and Atsushi Zukeran. EVALUATION OF THE START-UP CORE PHYSICS TESTS AT JAPAN'S HIGH TEMPERATURE ENGINEERING TEST REACTOR (FULLY-LOADED CORE). Office of Scientific and Technical Information (OSTI), March 2010. http://dx.doi.org/10.2172/974753.

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John D. Bess, Nozomu Fujimoto, Barbara H. Dolphin, Luka Snoj, and Atsushi Zukeran. Evaluation of the Start-Up Core Physics Tests at Japan's High Temperature Engineering Test Reactor (Fully-Loaded Core). Office of Scientific and Technical Information (OSTI), March 2009. http://dx.doi.org/10.2172/952014.

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Paul Demkowicz, Prateek Sachdev, Kevin DeWall, and Pavel Medvedev. High Temperature Steam Electrolysis Materials Degradation: Preliminary Results of Corrosion Tests on Ceramatec Electrolysis Cell Components. Office of Scientific and Technical Information (OSTI), June 2007. http://dx.doi.org/10.2172/933175.

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Lee, W. K., P. B. Fernandez, T. Graber, and L. Assoufid. High-heat-load synchrotron tests of room-temperature, silicon crystal monochromators at the CHESS F-2 wiggler station. Office of Scientific and Technical Information (OSTI), September 1995. http://dx.doi.org/10.2172/161514.

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Naus, D., J. Keeney-Walker, B. Bass, S. Iskander, R. Fields, R. deWit, and S. Low, III. High-temperature crack-arrest tests using 152-mm-thick SEN wide plates of low-upper-shelf base material: Tests WP-2. 2 and WP-2. 6. Office of Scientific and Technical Information (OSTI), February 1990. http://dx.doi.org/10.2172/7258827.

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Flaherty, Julia E., and John A. Glissmeyer. Tests of a High Temperature Sample Conditioner for the Waste Treatment Plant LV-S2, LV-S3, HV-S3A and HV-S3B Exhaust Systems. Office of Scientific and Technical Information (OSTI), March 2015. http://dx.doi.org/10.2172/1419159.

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Howard, Isaac, Thomas Allard, Ashley Carey, Matthew Priddy, Alta Knizley, and Jameson Shannon. Development of CORPS-STIF 1.0 with application to ultra-high performance concrete (UHPC). Engineer Research and Development Center (U.S.), April 2021. http://dx.doi.org/10.21079/11681/40440.

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This report introduces the first release of CORPS-STIF (Concrete Observations Repository and Predictive Software – Structural and Thermodynamical Integrated Framework). CORPS-STIF is envisioned to be used as a tool to optimize material constituents and geometries of mass concrete placements specifically for ultra-high performance concretes (UHPCs). An observations repository (OR) containing results of 649 mechanical property tests and 10 thermodynamical tests were recorded to be used as inputs for current and future releases. A thermodynamical integrated framework (TIF) was developed where the heat transfer coefficient was a function of temperature and determined at each time step. A structural integrated framework (SIF) modeled strength development in cylinders that underwent isothermal curing. CORPS-STIF represents a step toward understanding and predicting strength gain of UHPC for full-scale structures and specifically in mass concrete.
9

Aaron, Adam M., Richard Burns Cunningham, David L. Fugate, David Eugene Holcomb, Roger A. Kisner, Fred J. Peretz, Kevin R. Robb, Dane F. Wilson, and Graydon L. Yoder, Jr. High Temperature Fluoride Salt Test Loop. Office of Scientific and Technical Information (OSTI), December 2015. http://dx.doi.org/10.2172/1237612.

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Richard R. Schult, Paul D. Bayless, Richard W. Johnson, James R. Wolf, and Brian Woods. Scaling Studies for High Temperature Test Facility and Modular High Temperature Gas-Cooled Reactor. Office of Scientific and Technical Information (OSTI), February 2012. http://dx.doi.org/10.2172/1042382.

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