Relevant bibliographies by topics / Pressurized Condition

Academic literature on the topic 'Pressurized Condition'

Author: Grafiati
Published: 14 March 2023

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Journal articles on the topic "Pressurized Condition"

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Malaguez, Edgard Gonçalves, Andressa Tellechea Rodrigues, Kelli Flores Garcez, Gabriela Ceratti Hoch, Ana Paula Schmidt, Francisco Augusto Burkert Del Pino, and Deise Dalazen Castagnara. "Analysis of Fibrous Compounds Using a Pressurized and Non-pressurized Conditions." Journal of Agricultural Studies 8, no. 4 (November 4, 2020): 670. http://dx.doi.org/10.5296/jas.v8i4.17591.

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Neutral detergent fiber (NDF) and acid detergent fiber (ADF) contents were evaluated in pressurized and unpressurized conditions using samples of roughage and concentrates. In summary, the samples were dried, processed in a knife mill, weighed in nonwoven bags (100g/m²), placed in a container and treated with neutral or acid detergents. Extractions of NDF and ADF content were carried out in a non-pressurized condition at temperature of 100°C for 60min and in pressurized condition using different temperatures of 100 and 110°C for 60min. Results of the different temperatures using the pressurized procedure were compared to those obtained with the pressurized through the linear regression analysis. The method with the temperature 110°C for 60 min had a high level of agreement. Was not observed a bias potential of proportion (P>0.05). There was not a systematic inclination of the methods to overestimate or underestimate errors. This methodology can be carried out with roughage and concentrate feedstuffs simultaneously.
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Chen, Pengju, Stefan Z. Miska, Rui Ren, Mengjiao Yu, Evren Ozbayoglu, and Nicholas Takach. "Poroelastic modeling of cutting rock in pressurized condition." Journal of Petroleum Science and Engineering 169 (October 2018): 623–35. http://dx.doi.org/10.1016/j.petrol.2018.06.009.

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Kikuchi, Motokazu, Norikuni Yanagihara, Tetsuo Miyamoto, Mikio Kanzaki, and Shigeru Matsumoto. "Flow Properties of Whipped Cream under Pressurized Condition." KAGAKU KOGAKU RONBUNSHU 18, no. 5 (1992): 570–75. http://dx.doi.org/10.1252/kakoronbunshu.18.570.

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Shao, Xin Jie, Guang Tian, Jin Hua Liu, Jian Bin Zhang, Li Li Yang, and Yun Guang Qi. "Experimental Research on Sealing Structure Leak-Rate of Pressurized Tube." Advanced Materials Research 791-793 (September 2013): 523–26. http://dx.doi.org/10.4028/www.scientific.net/amr.791-793.523.

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In aerospace engineering, seal is an important component of manned spacecraft life-support system. The pressurized tube sealing equipment is designed, and the experimental system of principle leak-rate of pressurized tube is built, and the experimental theory of the principle leak-rate of pressurized tube is carried out. The experimental results show that leak-rate of pressurized tube is related with the internal pressure of pressurized tube, and sealing ability can be adjusted by controlling the pressure in tube. And leak-rate of pressurized tube is involved with sealed pressure differential, and the bigger pressure differential is, the larger leak-rate becomes. And pressurized tube can fit for big structure transfiguration, which provides condition for lessening structural weight. And the pressurized tube can meet the demands of sealing of space station.
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Kim, Young Ho, Hyo Sub Kim, Sang Jin Han, Chu Sik Park, Ki Kwang Bae, and Jong Gyu Lee. "Phase Separation Characteristics of Pressurized Bunsen Reaction for Sulfur-Iodine Thermochemical Hydrogen Production Process." Advanced Materials Research 550-553 (July 2012): 554–57. http://dx.doi.org/10.4028/www.scientific.net/amr.550-553.554.

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The Sulfur-Iodine (SI) thermochemical hydrogen production process is promising method for the massive production of hydrogen using the high temperature thermal energy of VHTR. For continuous operation of SI process, the conditions of Bunsen reaction are considered as the pressurized conditions with ca. 373~393K temperature and the composition of Bunsen products should be kept constant during the reaction. Therefore, we carried out the continuous Bunsen reaction using a counter-current flow reactor at pressurized condition to investigate the phase separation characteristics of pressurized Bunsen reaction. As the results, the composition of Bunsen product was maintained constantly as the evidence for the steady-state operation. The continuous reaction was operated without occurrence of side reactions, and a H2SO4 phase and HIx phase as the product contains a small amount of impurities (HI in a H2SO4 phase and H2SO4 in a HIx phase). We concluded that the pressurized Bunsen reaction is favorable to the continuous operation of SI process than the atmospheric reaction.
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ISHIBASHI, Masahiro, and Masaki TAKAMOTO. "Calibration of Super-Accurate Critical Nozzles at Pressurized Condition." Transactions of the Society of Instrument and Control Engineers 36, no. 1 (2000): 1–9. http://dx.doi.org/10.9746/sicetr1965.36.1.

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Asano, Koichi, and Yoshihiro Mugikura. "Degradation Behavior of Membrane in PEFCs under Pressurized Condition." ECS Transactions 25, no. 1 (December 17, 2019): 781–87. http://dx.doi.org/10.1149/1.3210630.

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Shatskyi, Ivan, Andrii Struk, and Maksym Vaskovskyi. "Static and Dynamic Stresses in Pipeline Built on Damaged Foundation." Transactions of the VŠB – Technical University of Ostrava, Civil Engineering Series. 17, no. 2 (December 1, 2017): 119–24. http://dx.doi.org/10.1515/tvsb-2017-0036.

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Abstract A deformation model of the buried pipeline under complicated geotechnical conditions of local ground failure is proposed. The effect of displacement of discontinuities in failed ground on the stressed condition and limited equilibrium of pressurized pipe has been studied.
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Wei, Jiafang, Yiyi Ma, David Z. Zhu, and Jian Zhang. "Effect of boundary conditions on the performance of a dropshaft with an internal divider." Water Science and Technology 2017, no. 2 (April 11, 2018): 441–49. http://dx.doi.org/10.2166/wst.2018.163.

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Abstract Dropshafts with an internal divider for air circulation are proposed to reduce air entrainment in plunging type dropshafts. Dropshafts typically operate under a pressurized downstream condition and with limited air supply from the top. In this study, experiments were conducted to investigate the performance of the dropshaft with an internal divider under different downstream conditions and air inlet conditions. From the experiments, a pressurized downstream condition would increase the air pressure in the dropshaft, reduce the outside air entrainment while increase the internal air circulation. Reducing the size of the air inlet would decrease the air pressure, meanwhile cause an increase in internal air circulation and a reduction in outside air entrainment. A dimensionless parameter of ‘effectiveness factor’ was also proposed to measure the effectiveness of the internal air circulation on reducing the outside air entrainment. This study considers the performance of the dropshaft with a divider under the conditions close to real situations, which is important to its design and application.
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Vinnakota, SRI Harsha Sri Harsha, R. Balaji, A. S. Brindha, Lakshman Neelakantan, and Krishnan Ramya. "Influence of Operating Parametres on PEM Based Ecmr for Hydrogen Production in Pressurised Condition." ECS Meeting Abstracts MA2022-02, no. 40 (October 9, 2022): 1462. http://dx.doi.org/10.1149/ma2022-02401462mtgabs.

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Hydrogen has the potential to promote the development of new, innovative and environmentally friendly solutions for future demands which would help for the smooth energy transition from fossil fuels. Though hydrogen has a high potential to replace fossil fuels, the challenges associated with the hydrogen value chain are in the production, storage, transportation and distribution stages. Electrolysis of water in PEM based system is a single step green hydrogen production process while integrated with renewable energy resources. However, this energy-intensive process makes the hydrogen production cost high and it is pave way for adopting the grey hydrogen or blue hydrogen production route as an intermediate stage for the transition from fossil fuel to hydrogen fuel economy. In this context PEM based Electrochemical Methanol Reformer (ECMR) technology has unique advantages such as low electrical energy consumption than water electrolysis and it can be easily integrated with renewable energy sources. Further, it can be operated at near ambient temperature and doesn’t require any hydrogen purification system, unlike a chemical reformer. Currently, PEM based water electrolyzer is producing pressurized hydrogen, which will eliminate the need for an external hydrogen compressor for its storage. Further, the influence of operating parameters on the operation of PEM water electrolyser under pressurised conditions is studied in the literature. However, this aspect of the study is not well studied and not much literature is available on PEM based ECMR systems. The present work, it is aimed to systematically study the effect of various operating parameters on the performance of ECMR under pressurised operation conditions and the obtained results are discussed. It shows the operation of ECMR under pressurised condition are promising and it will eliminate the need for an external H2 compressor system for hydrogen storage like PEM based water electrolyzer. Keywords: Hydrogen, PEM based Electrochemical reformer, pressurised hydrogen
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Dissertations / Theses on the topic "Pressurized Condition"

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Dumnernchanvanit, Ittinop. "Characterization and mitigation of crud at pressurized water reactor conditions." Thesis, Massachusetts Institute of Technology, 2017. http://hdl.handle.net/1721.1/115003.

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Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2017.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Cataloged from student-submitted PDF version of thesis.
Includes bibliographical references (pages 448-467).
The nuclear industry is no exception when it comes to those affected by fouling deposit problems. Fouling deposits on fuel rods in nuclear reactors, known as crud, can cause a variety of undesirable effects including axial power shifts, accelerated corrosion, increased primary circuit radiation dose, and possible fuel failure. This study revisits the crud problem once again using a newly constructed Internally Heated Testloop For PWRs (IHTFP) and new analytical techniques, and attempt to find a way to prevent or mitigate crud, or at least better understand it. This is the first time that fuelrod coatings are examined as a way of countering crud growth. These coatings are chosen based on their surface chemical properties and robustness at PWR conditions. For the goal of gaining a better understanding of crud, this study is the first to apply fractal analysis to characterize crud. To achieve both of these goals, the IHTFP was built to obtain crud grown under the PWR thermal-hydraulic and chemical conditions. The crud-resistant coatings experiments show significantly reduced crud surface coverage, indicating reduced crud adhesion, for TiC and ZrN coatings. The results roughly agree with London-van der Waals theoretical force predictions, suggesting that London-VDW forces are responsible for the adhesion of crud to fuel cladding. This knowledge can be useful in designing better crud-resistant materials. The fractal analysis can provide a simple, effective way to characterize the macro-scale behavior of crud with its micro-scale properties. The fractal analysis experimental study found R2 values to be very close to one when applying the box-counting method to crud, which is one piece of evidence to support the usage of fractal analysis on crud. Moreover, a strong logarithmic relationship trend between fractal dimension and porosity was found. This relationship applies to both the IHTFP's and Westinghouse loop's crud, even though the two experimental setups used different crud precursors and heat flux. This could indicate that crud's fractal dimension is dependent only on porosity. This relationship could simplify crud modeling and lead to better predictions of crud's behaviors. Better predictions can lower margins, leading to more efficient reactors.
by Ittinop Dumnernchanvanit.
Ph. D.
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Guo, Weiqing. "Miscibility and phase separation of polymer blends under normal and pressurised conditions." Thesis, Imperial College London, 1989. http://hdl.handle.net/10044/1/47460.

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Schmidt, Sebastian. "Entwicklung und Validierung eines Verfahrens zur Zustandsüberwachung des Reaktordruckbehälters während auslegungsüberschreitender Unfälle in Druckwasserreaktoren." Doctoral thesis, Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2018. http://nbn-resolving.de/urn:nbn:de:bsz:14-qucosa-235206.

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Für den zielgerichteten Einsatz von präventiven und mitigativen Notfallmaßnahmen sowie zur Beurteilung ihrer Wirksamkeit während auslegungsüberschreitender Unfälle in Druckwasserreaktoren aber auch für Hinweise zum Störfallverlauf und für die Abschätzung der Auswirkungen auf die Anlagenumgebung müssen geeignete Störfallinstrumentierungen vorhanden sein. Insbesondere der Zustand des Reaktordruckbehälterinventars (RDB-Inventar) während der In-Vessel-Phase eines auslegungsüberschreitenden Unfalls lässt sich mit aktuellen Störfallinstrumentierungen nur stark eingeschränkt überwachen, wodurch die o. g. Forderungen nicht erfüllt werden können. Die vorliegende Arbeit beinhaltet detaillierte Untersuchungen für die Entwicklung einer Störfallinstrumentierung, welche eine durchgängige Zustandsüberwachung des RDB-Inventars während der In-Vessel-Phase eines auslegungsüberschreitenden Unfalls ermöglicht. Die Störfallinstrumentierung basiert auf der Messung und Klassifikation von unterschiedlichen Gammaflussverteilungen, welche während der In-Vessel-Phase außerhalb des Reaktordruckbehälters auftreten können. Ausgehend von der Analyse zum Stand von Wissenschaft und Technik wird der modell-basierte Ansatz für Structural Health Monitoring-Systeme genutzt, um eine grundlegende Vorgehensweise für die Entwicklung der Störfallinstrumentierung zu erarbeiten. Anschließend erfolgt eine detaillierte Analyse zu den Vorgängen während der In-Vessel-Phase und eine daraus abgeleitete Definition von Kernzuständen für einen generischen Kernschmelzunfall. Für die definierten Kernzustände werden mittels Simulationen (Monte-Carlo-Simulationen zum Gammastrahlungstransport in einem zu dieser Arbeit parallel laufenden Vorhaben) Gammaflüsse außerhalb des Reaktordruckbehälters berechnet. Die Simulationsergebnisse dienen dem Aufbau von Datenbasen für die Entwicklung und Analyse eines Modells zur Klassifikation von Gammaflussverteilungen. Für die Entwicklung des Klassifikationsmodells kommen drei diversitäre und unabhängig arbeitende Klassifikationsverfahren (Entscheidungsbaum, k-nächste-Nachbarn-Klassifikation, Multilayer Perzeptron) zur Anwendung, um die Identifikationsgenauigkeit und Robustheit der Störfallinstrumentierung zu erhöhen. Die abschließenden Betrachtungen umfassen die Validierung der Störfallinstrumentierung mittels eines Versuchstandes zur Erzeugung unterschiedlicher Gammaflussverteilungen. Im Ergebnis der Untersuchungen konnte die prinzipielle Funktionsweise der entwickelten Störfallinstrumentierung nachgewiesen werden. Unter der Voraussetzung, die Gültigkeit der definierten Kernzustände zu untermauern sowie weitere, nicht in dieser Arbeit betrachtete Kernschmelzszenarien mit in die Entwicklung der Störfallinstrumentierung einzubeziehen, steht somit insbesondere für zukünftige Kernkraftwerke mit Druckwasserreaktoren eine Möglichkeit für die messtechnische Überwachung des RDB-Inventars während auslegungsüberschreitender Unfälle bereit. Die Arbeit leistet einen wesentlichen Beitrag auf dem Gebiet der Reaktorsicherheitsforschung sowie für den sicheren Betrieb von kerntechnischen Anlagen.
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Hawkes, Joshua Mahlon. "The Simulation and Study of Conditions Leading to Axial Offset Anomaly in Pressurized Water Reactors." Thesis, Georgia Institute of Technology, 2004. http://hdl.handle.net/1853/7612.

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Axial offset anomaly (AOA) in pressurized water reactors (PWR) refers to deviation of the measured neutron flux in the top half of the core from the predicted values. Among other difficulties, AOA reduces the shutdown margin, and may force the plant to reduce power output. AOA is believed to be caused by three related phenomena occurring in the core while operating at full power: sub-cooled nucleate boiling concentrated mainly in the upper half of the core, corrosion product deposition on the cladding surface (crud), and the deposition of boron within the porous crud layer in regions of vigorous sub-cooled boiling. This study replicates the conditions within the PWR primary coolant; specifically, the temperature, pressure, peak surface heat flux, coolant velocity and water chemistry are simulated in order to produce prototypical crud on an electrically heated Zircaloy-4 test element. At the conclusion of each test run, the heated Zircaloy-4 test element is rapidly isolated from the coolant in order to trap any soluble boron species that may be present in the crud layer. The results of this investigation indicate that prototypical crud with significant boron deposition can be produced. The deposited boron compound has been determined to be lithium tetraborate (Li2B4O7). Comparative experiments have been run to determine the effect of coolant pH, concentration and type of additives, and duration of exposure on the thickness of the crud deposit. The data obtained in this investigation can be used to validate mechanistic models for crud deposition and AOA in pressurized water reactors.
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Salnikova, Tatiana. "Two-phase CFD analyses in fuel assembly sub-channels of Pressurized Water Reactors under swirl conditions." Doctoral thesis, Saechsische Landesbibliothek- Staats- und Universitaetsbibliothek Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:14-qucosa-27307.

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Single-phase CFD calculations are already widely applied in nuclear industry for the thermal-hydraulic design optimization of fuel assemblies (FA). In contrast, two-phase CFD-applications are still in the state of development. The work presented in this thesis shows contributions towards the detailed two-phase modeling of boiling flows under swirl conditions in sub-channel geometries of pressurized water reactors (PWR) FAs, including a realistic description of the critical heat flux (CHF)-phenomena and identification of two-phase indicators characterizing CHF-phenomena. The numerical simulations were conducted with a 3-D CFD code (STAR CD) for various types of swirl generating components in FA. New insights regarding local void distribution in sub-channels under swirl conditions were obtained, which are relevant for CHF (“bubble pockets”). Furthermore, an enhanced wall partitioning model provides a more realistic description of the steep increase of the rod temperature due to CHF. Presented validation studies showed good agreement with the available experiments under PWR conditions for the radial void distributions at non-CHF conditions as well as for the CHF prediction. The results performed in this thesis show the incentives and chances of two-phase CFD applications for the development of thermal-hydraulically optimized PWR spacer grids with regard to heat transfer and improvement to the CHF behaviour
Einphasige CFD Analysen stellen für typische thermohydraulische Fragestellungen aus dem Kernkraftwerksbereich bereits jetzt ein wichtiges Werkzeug für die Brennelement (BE)¬Auslegung dar. Die zweiphasige CFD-Modellierung befindet sich dagegen in der Entwicklungsphase. Die in dieser Dissertation präsentierten Arbeiten zeigen Fortschritte für die detaillierte zweiphasige Modellierung drallbehafteter Strömungen im Unterkanal eines BEs des Druckwasserreaktors (DWR) einschließlich der realistischen Beschreibung des kritischen Wärmestroms (CHF) sowie die Bestimmung zweiphasiger Indikatoren, welche das Auftreten von CHF-Phänomen beschreiben. Verschiedene drallerzeugende Komponenten im BE wurden mit dem 3-D CFD-Code STAR-CD modelliert. Es wurden neue Erkenntnisse zur lokalen Blasenverteilung in Unterkanälen unter Drallbedingungen gewonnen, die für CHF relevant sind (“bubble pockets”). Durch eine Modifikation des Wärmeübergangsmodells (heat partitioning model) wird der starke Anstieg der Stabtemperatur infolge CHF realistischer beschrieben. Die durchgeführten Validierungen zeigen eine gute Übereinstimmung mit verfügbaren Experimenten unter DWR-Bedingungen für die radialen Blasenverteilungen und für die Bestimmung von CHF. Die vorliegenden Ergebnisse dieser Dissertation verdeutlichen den Nutzen und die Möglichkeiten von zweiphasigen CFD-Anwendungen für die Entwicklung und die thermohydraulische Optimierung von DWR-Abstandshaltern bezüglich des Wärmeübergangs und der Verbesserung des CHF-Verhaltens
Модели однофазовой среды в вычислительной гидродинамике (англ. CFD) являются уже сейчас важным инструментом для решения типичных термогидравлических задач в ядерной энергетике, например, при конструировании тепловыделяющих сборок (ТВС). Двухфазовое моделирование, в сравнении с однофазовым, находится на сегодняшний момент в стадии развития. Данная диссертация связана с совершенствованием двухфазовой модели в направлении улучшения детализации вихревого течения внутри ячейки ТВС в условиях работы двухконтурного ядерного реактора (тип PWR). Также в работе показана возможность более реалистичного описания феномена кризиса теплоотдачи и определения двухфазовых индикаторов, характеризующих критический тепловой поток (англ. CHF). Комплекс расчетов выполнен для различных интенсификаторов теплоотдачи, размещенных на дистанционирующих решетках TBC. Расчеты производились с помощью программного обеспечения STAR-CD, позволяющего моделировать трехмерные гидродинамические системы. Полученные новые данные о локальном распределении пузырьков в ячейках с вихревым течением дали важную информацию для идентификации критического теплового потока. Усовершенствование модели теплоотдачи на поверхности тепловыделяющего элемента (ТВЭЛ) позволило более реалистично описать резкое повышение температуры на поверхности ТВЭЛа при достижении критических условий. Полученные результаты численного моделирования для радиальных распределений пузырьков при нормальных условиях работы PWR и также для определения критического теплового потока показали хорошее совпадение с известными экспериментальными данными. Представленные в диссертации результаты показывают возможности применения двухфазовых CFD-расчётов для разработки и термогидравлической оптимизации дистанционирующих решеток с целью улучшения теплообмена и характеристик критического теплового потока в двухконтурном ядерном реакторе типа PWR
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Vereen, Keon. "An experimental investigation on the dynamics of bubbles utilizing refrigerant R134a under pressurized flow boiling conditions." Master's thesis, University of Central Florida, 2011. http://digital.library.ucf.edu/cdm/ref/collection/ETD/id/4717.

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Flow boiling heat transfer allows for the dissipation of large amounts of heat. In this work, the effect of heat flux and pressure on flow boiling of liquid refrigerant R-134a is studied in a vertical thin channel. The experimental setup mimics a refrigeration cycle and specifically looks at the effect of pressure and wall heat flux on the departure size and bubble generation rate. The experimental setup consists of a closed loop which includes a vertical narrow rectangular channel and two synchronized high speed cameras for optical measurements at either sides of the channel. The setup is built to employ an accurate measurement technique to define wall temperatures of the representative flow boiling process. Instead of using thermocouples on the surface channel, the thermochromic liquid crystallography (TLC) technique is used to determine non-invasively the heater surface temperature at high temporal and spatial resolution. The TLC interval range is 30-50??C. The TLC is attached to a Fecralloy heating section. The high speed Prosilica cameras simultaneously capture, colored TLC images as well as bubble nucleation and departure at very high frame rates. Experiments on subcooled flow boiling heat transfer have been conducted with refrigerant R-134a under a mass flux range of 484.838 kg/m??s to 1212.1 kg/m??s. With the low mass flux, the wall heat flux ranged from 167.2 to 672.1 kW/m??, the inlet subcooling ranged from 0.35??C to 16.55??C, the system pressure ranged from 621 kPa to 1034 kPa. At high mass flux, the wall heat flux ranged from 329.8 kW/m?? to 744 kW/m??, the inlet subcooling from 0.16??C to 17.21??C, and the system pressure from 621 kPa to 1034 kPa. A parametric study was done by maintaining various input parameters constant. From the high speed images, bubble parameters such as size and frequency are calculated. Temperature contours are utilized to determine the surface wall temperature at specific points.; Sequential wall temperatures are traced over a short period of time to understand the cooling effects. The bubble propagation and coalescence are also visualized. Results show that bubble size and frequency increased with heat flux at any particular pressure. At higher pressure, the trend would be for the bubble size to decrease; however, the inlet subcooling and heat flux also affect bubble size. The bubble frequency is also seen to be affected by the inlet subcooling and the heat flux. Even though the inlet subcooling is maintained approximately constant, any slight decrease in subcooling increased bubble growth rate. Another trend that is observed is that at higher the heat flux, the bubble generation frequency is faster; however no specific trend is observed for wall superheat. With an increase in heat flux, the wall superheats are expected to increase; however, the localized nature of the nucleation activity sites is seen to affect the results. The variables are non-dimensionalized to note trends in parameters. In summary, the data analysis demonstrates that both heat flux and pressure significantly influence the bubble generation rate, size, propagation and coalescence.
ID: 030646273; System requirements: World Wide Web browser and PDF reader.; Mode of access: World Wide Web.; Thesis (M.S.A.E.)--University of Central Florida, 2011.; Includes bibliographical references (p. 107-115).
M.S.A.E.
Masters
Mechanical and Aerospace Engineering
Engineering and Computer Science
Aerospace Engineering; Thermofluid Aerodynamics Systems Track
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7

Salnikova, Tatiana. "Two-phase CFD analyses in fuel assembly sub-channels of Pressurized Water Reactors under swirl conditions." Doctoral thesis, Salnikova, T.: Two-phase CFD analyses in fuel assembly sub-channels of Pressurized Water Reaktors under swirl conditions. Fortschr.-Ber. VDI Reihe 7 Nr. 497. Düsseldorf: VDI-Verlag 2010. ISBN 978-3-18-349707-2, ISSN 0178-9538, 2008. https://tud.qucosa.de/id/qucosa%3A25245.

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Single-phase CFD calculations are already widely applied in nuclear industry for the thermal-hydraulic design optimization of fuel assemblies (FA). In contrast, two-phase CFD-applications are still in the state of development. The work presented in this thesis shows contributions towards the detailed two-phase modeling of boiling flows under swirl conditions in sub-channel geometries of pressurized water reactors (PWR) FAs, including a realistic description of the critical heat flux (CHF)-phenomena and identification of two-phase indicators characterizing CHF-phenomena. The numerical simulations were conducted with a 3-D CFD code (STAR CD) for various types of swirl generating components in FA. New insights regarding local void distribution in sub-channels under swirl conditions were obtained, which are relevant for CHF (“bubble pockets”). Furthermore, an enhanced wall partitioning model provides a more realistic description of the steep increase of the rod temperature due to CHF. Presented validation studies showed good agreement with the available experiments under PWR conditions for the radial void distributions at non-CHF conditions as well as for the CHF prediction. The results performed in this thesis show the incentives and chances of two-phase CFD applications for the development of thermal-hydraulically optimized PWR spacer grids with regard to heat transfer and improvement to the CHF behaviour.
Einphasige CFD Analysen stellen für typische thermohydraulische Fragestellungen aus dem Kernkraftwerksbereich bereits jetzt ein wichtiges Werkzeug für die Brennelement (BE)¬Auslegung dar. Die zweiphasige CFD-Modellierung befindet sich dagegen in der Entwicklungsphase. Die in dieser Dissertation präsentierten Arbeiten zeigen Fortschritte für die detaillierte zweiphasige Modellierung drallbehafteter Strömungen im Unterkanal eines BEs des Druckwasserreaktors (DWR) einschließlich der realistischen Beschreibung des kritischen Wärmestroms (CHF) sowie die Bestimmung zweiphasiger Indikatoren, welche das Auftreten von CHF-Phänomen beschreiben. Verschiedene drallerzeugende Komponenten im BE wurden mit dem 3-D CFD-Code STAR-CD modelliert. Es wurden neue Erkenntnisse zur lokalen Blasenverteilung in Unterkanälen unter Drallbedingungen gewonnen, die für CHF relevant sind (“bubble pockets”). Durch eine Modifikation des Wärmeübergangsmodells (heat partitioning model) wird der starke Anstieg der Stabtemperatur infolge CHF realistischer beschrieben. Die durchgeführten Validierungen zeigen eine gute Übereinstimmung mit verfügbaren Experimenten unter DWR-Bedingungen für die radialen Blasenverteilungen und für die Bestimmung von CHF. Die vorliegenden Ergebnisse dieser Dissertation verdeutlichen den Nutzen und die Möglichkeiten von zweiphasigen CFD-Anwendungen für die Entwicklung und die thermohydraulische Optimierung von DWR-Abstandshaltern bezüglich des Wärmeübergangs und der Verbesserung des CHF-Verhaltens.
Модели однофазовой среды в вычислительной гидродинамике (англ. CFD) являются уже сейчас важным инструментом для решения типичных термогидравлических задач в ядерной энергетике, например, при конструировании тепловыделяющих сборок (ТВС). Двухфазовое моделирование, в сравнении с однофазовым, находится на сегодняшний момент в стадии развития. Данная диссертация связана с совершенствованием двухфазовой модели в направлении улучшения детализации вихревого течения внутри ячейки ТВС в условиях работы двухконтурного ядерного реактора (тип PWR). Также в работе показана возможность более реалистичного описания феномена кризиса теплоотдачи и определения двухфазовых индикаторов, характеризующих критический тепловой поток (англ. CHF). Комплекс расчетов выполнен для различных интенсификаторов теплоотдачи, размещенных на дистанционирующих решетках TBC. Расчеты производились с помощью программного обеспечения STAR-CD, позволяющего моделировать трехмерные гидродинамические системы. Полученные новые данные о локальном распределении пузырьков в ячейках с вихревым течением дали важную информацию для идентификации критического теплового потока. Усовершенствование модели теплоотдачи на поверхности тепловыделяющего элемента (ТВЭЛ) позволило более реалистично описать резкое повышение температуры на поверхности ТВЭЛа при достижении критических условий. Полученные результаты численного моделирования для радиальных распределений пузырьков при нормальных условиях работы PWR и также для определения критического теплового потока показали хорошее совпадение с известными экспериментальными данными. Представленные в диссертации результаты показывают возможности применения двухфазовых CFD-расчётов для разработки и термогидравлической оптимизации дистанционирующих решеток с целью улучшения теплообмена и характеристик критического теплового потока в двухконтурном ядерном реакторе типа PWR.
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Rebak, Raúl Basilio. "Environmentally induced cracking in alloy 600 and SA 302 steel in pressurized water reactor steam generator conditions /." The Ohio State University, 1993. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487846885777343.

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Byakika, Stephen Nyende. "Modelling of Pressurised Water Supply Networks that May Exhibit Transient Low Pressure - Open Channel Flow Conditions." Thesis, Vaal University of Technology, 2011. http://hdl.handle.net/10352/421.

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D. Tech. (Department of Civil Engineering and Building, Faculty of Engineering and Technology), Vaal University of Technology
Growing demand for water due to increasing populations, industrialisation and water consuming lifestyles puts stress on existing water supply systems. To cater for the rising demand, water distribution networks are expanded beyond their design capacities and this creates transient “low-pressure-open-channel flow” (LPOCF) conditions. Current water supply models use “demand driven approach” (DDA) methodology which is not able to simulate transient LPOCF conditions, that poses an impediment to management/analysis of pressure-deficient networks. With a case study of the water supply network of Kampala City, LPOCF conditions were studied in this research. A “pressure/head driven approach” (PDA/HDA) was used in order to determine what demand is enabled by particular nodal pressures. Conversion of free surface to pressurised flow was analysed and modelled, with a view to clearly understanding occurrence of this phenomenon. The research demonstrated that if adequate pressures and flows are to be maintained, effectiveness of the water distribution network should be given as much attention as water production capacity. The research also indicated that when network pressures are low, the head-driven approach to water distribution modelling gives more accurate results than the traditional demand-driven methodology. Coexistence of free-surface and pressurised flow in networks prone to LPOCF conditions was confirmed and modelled. Results obtained highlighted the advantages of developing fully dynamic and transient models in the solution of transient LPOCF conditions in water distribution networks. Models developed allow application of PDA/HDA and DDA methodologies in systems that may exhibit LPOCF conditions thus enabling identification, understanding and analysis of the status of all sections of the network. These culminated in the development of a DSS to guide operational decisions that can be made to optimise network performance.
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Wang, Mi. "Electrochemical Behaviour of Stainless Steel under Radiation and Exposed to Representative Chemistry in Pressurised Water Reactor Conditions." Palaiseau, Ecole polytechnique, 2013. http://pastel.archives-ouvertes.fr/docs/00/91/55/75/PDF/Mi_WANG_thesis.pdf.

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Cette thèse est dédiée à l'étude du comportement des aciers inoxydables sous irradiation exposés en condition primaire des réacteurs à eau pressurisée (REP). Le potentiel électrochimique de l'acier inoxydable austénitique 316L et les paramètres environnementaux comme la teneur en hydrogène, ont été mesurés de façon continue à haute température (HT) et haute pression (HT) grâce à un dispositif expérimental unique, la cellule HTHP. Deux sources d'irradiation ont été utilisées: les protons et les électrons. Le comportement électrochimique du 316L s'est avéré similaire dans les deux cas: (i) une augmentation du potentiel sous irradiation de l'ordre de la dizaine de millivolts ("réponse oxydative"); (ii) l'augmentation de la teneur en hydrogène diminue cette augmentation du potentiel sous irradiation; (iii) une synergie est observée entre le vieillissement à 300 C et la fluence qui conduit également à limiter la réponse oxydative sous irradiation. Les observations du film passif d'oxydes mettent en évidence la présence de nickel métallique dans l'ensemble des oxydes (interne et externe) en présence d'hydrogène, sans irradiation. Après les irradiations les plus fortes, des cavités (piqûres) sont observées en surface du 316L. Ces défauts sont attribués à l'effet de la radiolyse de l'eau et de l'irradiation de la couche passive. La radiolyse influence également l'évolution de la chimie du milieu primaire qui devient plus acide et plus oxydante. Il en résulte une augmentation du relâchement des cations métalliques et la présence d'hématite ( a-Fe2O3) sur le film d'oxyde externe de l'acier inoxydable lorsque les cavités (piqûres) sont formées
The dissertation focuses on the behaviour of stainless steel under irradiation and exposed to primary PWR conditions. The electrochemical potential of austenitic 316L stainless steel and the environmental parameters (hydrogen pressure, temperature, etc. ,) have been measured continuously at high temperature (HT) and high pressure (HP) under irradiation, using a unique experimental HTHP working cell. Two sources of irradiation, proton and electron beams, have been employed in the study. A high similarity of electrochemical behaviour under both types of irradiations has been observed: (i) an oxidative potential response under irradiation (few tens of millivolts); (ii) an increase in the hydrogen pressure reduces the oxidative potential response; (iii) a synergetic effect of thermal ageing and fluence leading to a decrease of the oxidative response under irradiation. The observations of the oxide film showed that without irradiation, metallic nickel in the inner and outer oxide films has been observed under a high hydrogen pressure. Under irradiation, um scale cavities (pits) have been observed in the strongly electron irradiated oxide film formed on 316L stainless steel. These defects are induced by the effect of irradiation of the passive film and water radiolysis. It is also shown that water radiolysis influences the PWR water chemistry by making it become a stronger oxidant at the oxide/solution interface. As a result, the release of metallic cations is increased and a-Fe2O3 hematite has been observed on the irradiated outer oxide film where cavities were formed
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Books on the topic "Pressurized Condition"

1

P, Majumdar, and Bhabha Atomic Research Centre, eds. Development of a program "BFQ/VERI" to simulate vapour pull through and liquid entrainment under stratified flow condition. Mumbai: Bhabha Atomic Research Centre, 2000.

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Centre, Bhabha Atomic Research, ed. Study of hydride blisters grown on Zr-2.5Nb pressure tube spool piece under simulated condition of in-reactor pressure and temperature. Mumbai: Bhabha Atomic Research Centre, 2005.

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Pugh, C. E. A review of large-scale fracture experiments relevant to pressure vessel integrity under pressurized thermal shock conditions. Washington, DC: U.S. Nuclear Regulatory Commission, 2001.

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R, Bass B., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., and Oak Ridge National Laboratory, eds. A review of large-scale fracture experiments relevant to pressure vessel integrity under pressurized thermal shock conditions. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2001.

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S, Martorell, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, and Universidad Politécnica de Valencia. Departamento de Ingenieria Quimica y Nuclear, eds. Simulation of LOCA 6" and LOCA 2" transients in the RHR of a PWR under low power conditions using RELAP5/MOD3.2. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2000.

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J, Shack W., and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology., eds. Behavior of PWR reactor coolant system components, other than steam generator tubes, under severe accident conditions: Phase I final report. Washington, DC: Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2003.

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A, Yegorova L., U.S. Nuclear Regulatory Commission., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Joint Stock Company "TVEL", Institut problem bezopasnogo ispolʹzovanii︠a︡ i︠a︡dernoĭ ėnergii (Rossiĭskiĭ nauchnyĭ t︠s︡entr "Kurchatovskiĭ institut"), Institut de radioprotection et de sûreté nucléaire., and Gosudarstvennyĭ nauchnyĭ t︠s︡entr Rossiĭskoĭ Federat︠s︡ii "Nauchno-issledovatelʹskiĭ institut atomnykh reaktorov", eds. Experimental study of embrittlement of Zr-1%Nb VVER cladding under LOCA-relevant conditions. Washington, D.C: U.S. Nuclear Regulatory Commission, 2005.

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R, Bass B., Oak Ridge National Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering., eds. A comparison of analysis methodologies for predicting cleavage arrest of a deep crack in a reactor pressure vessel subjected to pressurized-thermal-shock loading conditions. Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1992.

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VanWinkle, James A. Oxidation of Zircaloy-4 in pressurized water reactor conditions. 1989.

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VanWinkle, James A. Oxidation of Zircaloy-4 in pressurized water reactor conditions. 1989.

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Book chapters on the topic "Pressurized Condition"

1

Delgado-Aguiñaga, Jorge A., and Ofelia Begovich. "Water Leak Diagnosis in Pressurized Pipelines: A Real Case Study." In Applied Condition Monitoring, 235–62. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-55944-5_12.

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Fersi, Mohamed, and Ali Triki. "Alternative Design Strategy for Water-Hammer Control in Pressurized-Pipe Flow." In Applied Condition Monitoring, 157–65. Cham: Springer International Publishing, 2018. http://dx.doi.org/10.1007/978-3-319-94616-0_16.

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Pop, Mike G., Merl Bell, and Brian Lockamon. "AREVA Fuel Condition Index for a Pressurized Water Reactor." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors, 665–69. Cham: Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_41.

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Pop, Mike G., Merl Bell, and Brian Lockamon. "Areva Fuel Condition Index for a Pressurized Water Reactor." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 665–69. Hoboken, New Jersey, Canada: John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch69.

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Zhu, Weibin, Shijian Ju, and Hui Wang. "Auxiliary Tunneling Technologies by Using Pressurized Air." In Shield Tunneling Technology in Mixed Face Ground Conditions, 447–55. Singapore: Springer Nature Singapore, 2022. http://dx.doi.org/10.1007/978-981-19-4112-2_14.

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Guzenberg, A. S. "Maintenance of Thermal Conditions in Pressurized Spacecraft Cabins." In Space Biology and Medicine – Volume II, Life Support and Habitability, 209–22. Reston ,VA: American Institute of Aeronautics and Astronautics, Inc., 1994. http://dx.doi.org/10.2514/5.9781624104664.0209.0222.

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Chang, I., G.-C. Cho, and A. T. P. Tran. "Application of biopolymer hydrogel for ground hydraulic conductivity control under pressurized conditions." In Geotechnical Aspects of Underground Construction in Soft Ground. 2nd Edition, 761–64. 2nd ed. London: CRC Press, 2022. http://dx.doi.org/10.1201/9781003355595-100.

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Moilanen, A., and K. Saviharju. "Gasification Reactivities of Biomass Fuels in Pressurised Conditions and Product Gas Mixtures." In Developments in Thermochemical Biomass Conversion, 828–37. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-009-1559-6_66.

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Kirchheck, Daniel, Dominik Saile, and Ali Gülhan. "Rocket Wake Flow Interaction Testing in the Hot Plume Testing Facility (HPTF) Cologne." In Notes on Numerical Fluid Mechanics and Multidisciplinary Design, 145–62. Cham: Springer International Publishing, 2020. http://dx.doi.org/10.1007/978-3-030-53847-7_9.

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Abstract Rocket wake flows were under investigation within the Collaborative Research Centre SFB/TRR40 since the year 2009. The current paper summarizes the work conducted during its third and final funding period from 2017 to 2020. During that phase, focus was laid on establishing a new test environment at the German Aerospace Center (DLR) Cologne in order to improve the similarity of experimental rocket wake flow–jet interaction testing by utilizing hydrogen–oxygen combustion implemented into the wind tunnel model. The new facility was characterized during tests with the rocket combustor model HOC1 in static environment. The tests were conducted under relevant operating conditions to demonstrate the design’s suitability. During the first wind tunnel tests, interaction of subsonic ambient flow at Mach 0.8 with a hot exhaust jet of approx. 920 K was compared to previously investigated cold plume interaction tests using pressurized air at ambient temperature. The comparison revealed significant differences in the dynamic response of the wake flow field on the different types of exhaust plume simulation.
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Tomishige, Keiichi, Yuichi Matsuo, Mohammad Asadullah, Yusuke Yoshinaga, Yasushi Sekine, and Kaoru Fujimoto. "Methane Reforming with Carbon Dioxide and Oxygen under Atmospheric and Pressurized Conditions Using Fixed- and Fluidized-Bed Reactors." In ACS Symposium Series, 303–15. Washington, DC: American Chemical Society, 2002. http://dx.doi.org/10.1021/bk-2002-0809.ch020.

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Conference papers on the topic "Pressurized Condition"

1

Mohammad, Suria Melanie, Kumar Nathan, and Ko Ko Kyi. "Wireline Logging under Pressurized Mud Cap Drilling Condition - A Challenging Operation." In SPE/IATMI Asia Pacific Oil & Gas Conference and Exhibition. Society of Petroleum Engineers, 2017. http://dx.doi.org/10.2118/186374-ms.

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Das, Kaushik, Todd Mintz, and Debashis Basu. "Numerical Evaluation of Corrosion Condition for Pressurized Water Reactor Secondary Cooling System." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57819.

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Flow-accelerated corrosion (FAC) in a pressurized water reactor (PWR) feedwater piping system is considered the leading degradation process that has been blamed for a number of accidents and incidents. One of the challenging issues in estimating FAC in piping is the hydrazine (N2H4) oxygen (O2) reaction rate and its subsequent impact on the wall mass transfer. N2H4 is injected in the system to maintain a stable pH in the water and also to act as an O2 scavenger. Previous research results indicate a varying degree of FAC rate dependence on the presence of N2H4 in the system. The N2H4-O2 reaction is also a complex function of temperature and pipe material. The present paper presents a two-part analysis that uses computational fluid dynamics (CFD) tools to investigate the N2H4-O2 reaction and its subsequent impact on mass transfer. In the first part of the analysis, chemistry and flow of water with dissolved O2 and N2H4 is simulated to assess different reaction mechanisms available in the literature. Results obtained from this study are compared with available experimental data for benchmarking. The numerical results were able to capture the general pattern of reaction rate as a function of temperature. Numerical simulations were also carried out to accommodate the surface effects on the reaction, but results indicate that such accommodations will yield useful results only if the geometrical extent of the near-wall-zone, where surface effects are prevalent, is well known. In the second part of the analysis, numerical simulations were carried out for a U-bend pipe. A number of restrictive assumptions were made to assess the dependence of O2 mass-transfer rate on N2H4-O2 reaction. Hydrodynamic results show the secondary flow pattern within the bend section. Results are also presented for the Sherwood number ratio at the pipe wall with and without reaction. Results indicate that the N2H4-O2 reaction decreases the O2 flow rate toward the wall. This calculation also shows that secondary flow in the bend affects the wall mass transfer pattern.
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Dong, Bing, Leihao Li, Chenyue Li, Junlian Yin, and Dezhong Wang. "CFD Simulation of Fission Gas Release Under Fuel Defects Condition in Pressurized Water Reactor." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81398.

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During normal pressurized water reactor (PWR) operation, the fuel cladding is inevitably defective. It is important to develop a model to evaluate the fission gas (FG) release from the fuel-cladding gap into the coolant, which benefits the fuel failure monitoring and improves the reactor safety. The objective of this paper is to give an overview of three-dimensional two-phase transient CFD simulation based on the Volume of Fluid (VOF) method to evaluate the fission gas migrating inside the gap and escaping through the defects. The topics of this paper include the behavior and release rate of FG in the fuel-cladding gap when the fuel cladding is defective. An analysis is presented on the suitability of the CFD simulation and it is shown that three-dimensional two-phase transient CFD simulation can be utilized in evaluating the FG release process. The results show that water enters the gap immediately after an abrupt cladding defect. The entering water flashes and causes pressure pulsation, which induces the transient FG release.
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Chou, Hsoung-Wei, and Chin-Cheng Huang. "Structural Reliability Evaluation on the Pressurized Water Reactor Pressure Vessel Under Pressurized Thermal Shock Events." In ASME 2014 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/pvp2014-28350.

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The failure probability of the pressurized water reactor pressure vessel for a domestic nuclear power plant in Taiwan has been evaluated according to the technical basis of the USNRC’s new pressurized thermal shock (PTS) screening criteria. The ORNL’s FAVOR code and the PNNL’s flaw models are employed to perform the probabilistic fracture mechanics analysis based on the plant specific parameters of the domestic reactor pressure vessel. Meanwhile, the PTS thermal hydraulic and the probabilistic risk assessment data analyzed from a similar nuclear power plant in the United States for establishing the new PTS rule are applied as the loading condition. Besides, an RT-based regression formula derived by the USNRC is also utilized to verify the through-wall cracking frequencies. It is found that the through-wall cracking of the analyzed reactor pressure vessel only occurs during the PTS events resulted from the stuck-open primary safety relief valves that later reclose, but with only an insignificant failure risk. The results indicate that the Taiwan domestic PWR reactor pressure vessel has sufficient structural margin for the PTS attack until either the end-of-license or for the proposed extended operation.
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Song, Jia-Wen, Meng-Chen Ma, and Li-Wu Fan. "Temperature Dependence of the Contact Angle of Water on a Hydrophobic Surface at Pressurized Condition." In ASME 2020 Heat Transfer Summer Conference collocated with the ASME 2020 Fluids Engineering Division Summer Meeting and the ASME 2020 18th International Conference on Nanochannels, Microchannels, and Minichannels. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/ht2020-8925.

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Abstract It is of both practical and scientific significance to study the temperature dependence of contact angles, towards development of surface wettability manipulation techniques for enhanced phase change heat transfer as well as the theoretical estimation of solid interfacial energy. However, the variations of surface wettability of a hydrophobic solid with altering temperature remain unclear. In this work, in situ characterizations of the contact angle of water on Teflon (PTFE) surfaces as well as the surface tension of water over a temperature spectrum from ∼25 °C to 160 °C at pressurized condition (2 MPa) were conducted by employing the sessile drop and pendant drop methods, respectively. A nearly invariant trend of the contact angle of water was observed over the entire temperature range. Moreover, it was shown that the surface tension of water linearly declines with raising the temperature. Based on the theory of surface thermodynamics, the effects of temperature on the contact angles were analyzed with the variations of interfacial tensions.
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Kiger, C. J., B. D. Shumaker, W. S. Johnson, and H. M. Hashemian. "Expanding the capabilities of wireless condition monitoring sensors into the containment of pressurized water reactors." In 2012 Future of Instrumentation International Workshop (FIIW). IEEE, 2012. http://dx.doi.org/10.1109/fiiw.2012.6378326.

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Larosa, Luca, Alberto Traverso, and Valentina Zaccaria. "Ambient Temperature Impact on Pressurized SOFC Hybrid Systems." In ASME Turbo Expo 2015: Turbine Technical Conference and Exposition. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/gt2015-42364.

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In this paper advanced control strategies based on Model Predictive Control (MPC) method are compared against a traditional PID controller in a Gas Turbine Pressurized SOFC hybrid system. A model of the integrated mGT-SOFC hybrid system has been developed to analyze the impact of ambient temperature changes on system performance and dynamic behaviour. Four different MIMO controllers (multi input multi output) based on a linearized system model have been implemented in order to control fuel cell temperature and power with different ambient temperatures. Fuel cell temperature is regulated by manipulating the cell by-pass mass flow, while power is regulated by changing the fuel cell electrical current and fuel mass flow (the fuel utilization factor is kept constant). Load following simulations have been carried out as follows: the same load ramp from 100% to 80% of fuel cell power and back has been set and studied under three different ambient conditions, 263K, 288K and 313K (−10°C, 15°C and 40°C). MPC demonstrated superior performance over the two distributed PID controls, thanks to the better setpoint tracking on the cell temperature, which is particularly evident when the ambient temperature deviates from the nominal condition. This is mainly explained by the capability of MPC in including the effects of non-linearities of the real system.
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Zeng, Dong-Lei, Biao Feng, Jia-Wen Song, and Li-Wu Fan. "Temperature-Dependent Wettability of Water on a Nickel Surface at Pressurized Condition: A Molecular Dynamics Study." In ASME 2019 Heat Transfer Summer Conference collocated with the ASME 2019 13th International Conference on Energy Sustainability. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/ht2019-3521.

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Abstract Temperature-dependent wettability of water droplets on a metal surface in a pressurized environment is of great theoretical and practical significance. In this paper, molecular dynamic simulation is used to study this problem by relating the temperature-dependent apparent contact angles to the changes in solid-liquid and solid-vapor interfacial free energies and hydrogen bonds in the nano-sized water droplets with increasing the temperature. The temperature range of interest is set from 298 K to 538 K in a 20 K interval under a constant pressure of 7 MPa. The results show that the contact angle in general decreases with raising the temperature and decreasing trend can be divided into two sections with different slopes. The contact angle drops slowly when the temperature is below 458 K as a critical point. Beyond this point, the contact angle shows a much steeper decrease. The difference between solid-vapor and solid-liquid interfacial free energies is found to decrease slightly with temperature. Combining with that the surface tension drops with increasing the temperature, a decreasing trend of the contact angle is expected according to the Young’s equation. As the temperature increases, the number and average energy of the hydrogen bonds both decrease, and the hydrogen bonds tend to aggregate at the bottom of the nano-droplets.
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9

Griesbach, Timothy J., Robert E. Nickell, H. T. Tang, and Jeff D. Gilreath. "Aging Management Strategies for Pressurized Water Reactor Vessel Internals." In ASME/JSME 2004 Pressure Vessels and Piping Conference. ASMEDC, 2004. http://dx.doi.org/10.1115/pvp2004-3055.

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Management of materials aging effects, such as loss of material, reduction in fracture toughness, or cracking, depends upon the demonstrated capability to detect, evaluate, and potentially correct conditions that could affect function of the internals during the license renewal term. License renewal applicants in their submittals to NRC have identified the general elements of aging management programs for Pressurized Water Reactor (PWR) internals, including the use of inservice inspection and monitoring with the possibility of enhancement or augmentation if a relevant condition is discovered. As plants near the license renewal term, plant-specific aging management programs will be implemented focusing on those regions most susceptible to aging degradation. A framework for the implementation of an aging management program is proposed in this paper. This proposed framework is based on current available research results and state of knowledge and utilizes inspections and flaw tolerance evaluations to manage the degradation issues. The important elements of this framework include: • The screening of components for susceptibility to the aging mechanisms, • Performing functionality analyses of the components with representative material toughness properties under PWR conditions, • Evaluating flaw tolerance of lead components or regions of greatest susceptibility to cracking, loss of toughness, or swelling, and • Using focused inspections to demonstrate no loss of integrity in the lead components or regions of the vessel internals. The EPRI Material Reliability Program (MRP) Reactor Internals Issue Task Group (RI-ITG) is actively working to develop the data and methods to quantify an understanding of aging and potential degradation of reactor vessel internals, to develop materials/components performance criteria, and to provide utilities tools for extending plant operations. Under this MRP Program, the technical basis for the framework will be documented. Then, based on that technical basis, PWR internals inspection and flaw evaluation guidelines will be developed for plants to manage reactor internals aging and associated potential degradation.
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10

Qingsen, Zhao, Liang Junqin, Zhou Shuai, Chen Jie, Zeng Weipeng, and Zhang Qiang. "Research on Spacing Design Method of Condenser Half-Side Operation in Pressurized Water Reactor Nuclear Power Plant." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-93265.

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Abstract The condenser of Pressurized Water Reactor (PWR) nuclear power plant in China has many cooling tube leakage events, resulting in serious safety impact and economic loss. One of the main reasons is the fluidelastic instability caused by the large support plate spacing in half side operation. The corresponding calculation model is not given in the design specifications. Combined with the basic theory of cooling pipe vibration and comprehensively comparing different support plate spacing design and calculation methods, the mathematical model used in support plate spacing calculation in Heat Exchange Institute (HEI) standards is deduced. On this basis, the support plate spacing calculation model of condenser half side operation in PWR nuclear power plant is proposed. Based on a pressurized water reactor nuclear power project, the calculation and verification are carried out under four working conditions: Turbine Maximum Continuous Rating condition (TMCR), Winter Continuous Rating condition (WCR), Winter condenser half side operation condition (WHS) and Winter load shedding condition (WLS). In this project, the support plate spacing under winter condenser half side operation condition was 663.67mm, which is the most dangerous working condition under four working conditions. It is suggested that the final conservative support plate spacing should be determined according to the most stringent working conditions in the condenser support plate spacing design of nuclear power plant. Using the evaluation models of Alstom and Westhouse, the condenser support plate spacing of the PWR nuclear power plant project is checked and verified. The support plate spacing obtained by the mathematical model is relatively conservative and safe. The physical meaning of this method is clear and easy to use. It has certain guiding significance for the support plate spacing design of condensers in PWR nuclear power plants in China.
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Reports on the topic "Pressurized Condition"

1

Pugh, C. E. A Review of Large-Scale Fracture Experiments Relevant to Pressure Vessel Integrity Under Pressurized Thermal Shock Conditions. Office of Scientific and Technical Information (OSTI), January 2001. http://dx.doi.org/10.2172/777631.

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2

Mohanty, Subhasish, Jae Phil Park, Daniel Franken, Joseph T. Listwan, Saurin Majumdar, and Ken Natesan. A Deterministic and Probabilistic Framework for Forecasting of Time-Series Damage States and Associated End-of-lIfe of a Pressurizer Water Reactor Surge Line under Design-Basis and Grid-Load-Following Loading Conditions. Office of Scientific and Technical Information (OSTI), September 2018. http://dx.doi.org/10.2172/1557591.

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