Добірка наукової літератури з теми "Pressurized Condition"
Оформте джерело за APA, MLA, Chicago, Harvard та іншими стилями
Ознайомтеся зі списками актуальних статей, книг, дисертацій, тез та інших наукових джерел на тему "Pressurized Condition".
Біля кожної праці в переліку літератури доступна кнопка «Додати до бібліографії». Скористайтеся нею – і ми автоматично оформимо бібліографічне посилання на обрану працю в потрібному вам стилі цитування: APA, MLA, «Гарвард», «Чикаго», «Ванкувер» тощо.
Також ви можете завантажити повний текст наукової публікації у форматі «.pdf» та прочитати онлайн анотацію до роботи, якщо відповідні параметри наявні в метаданих.
Статті в журналах з теми "Pressurized Condition"
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.
Повний текст джерелаChen, 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.
Повний текст джерелаKikuchi, 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.
Повний текст джерелаShao, 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.
Повний текст джерелаKim, 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.
Повний текст джерелаISHIBASHI, 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.
Повний текст джерелаAsano, 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.
Повний текст джерелаShatskyi, 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.
Повний текст джерелаWei, 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.
Повний текст джерелаVinnakota, 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.
Повний текст джерелаДисертації з теми "Pressurized Condition"
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.
Повний текст джерелаThis 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.
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.
Повний текст джерелаSchmidt, 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.
Повний текст джерелаHawkes, 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.
Повний текст джерелаSalnikova, 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.
Повний текст джерелаEinphasige 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
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.
Повний текст джерелаID: 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
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.
Повний текст джерелаEinphasige 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.
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.
Повний текст джерелаByakika, 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.
Повний текст джерелаGrowing 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.
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.
Повний текст джерелаThe 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
Книги з теми "Pressurized Condition"
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.
Знайти повний текст джерелаCentre, 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.
Знайти повний текст джерелаPugh, 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.
Знайти повний текст джерелаR, 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.
Знайти повний текст джерелаS, 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.
Знайти повний текст джерелаJ, 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.
Знайти повний текст джерелаA, 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.
Знайти повний текст джерелаR, 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.
Знайти повний текст джерелаVanWinkle, James A. Oxidation of Zircaloy-4 in pressurized water reactor conditions. 1989.
Знайти повний текст джерелаVanWinkle, James A. Oxidation of Zircaloy-4 in pressurized water reactor conditions. 1989.
Знайти повний текст джерелаЧастини книг з теми "Pressurized Condition"
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.
Повний текст джерелаFersi, 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.
Повний текст джерелаPop, 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.
Повний текст джерелаPop, 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.
Повний текст джерелаZhu, 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.
Повний текст джерелаGuzenberg, 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.
Повний текст джерелаChang, 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.
Повний текст джерелаMoilanen, 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.
Повний текст джерелаKirchheck, 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.
Повний текст джерелаTomishige, 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.
Повний текст джерелаТези доповідей конференцій з теми "Pressurized Condition"
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.
Повний текст джерелаDas, 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.
Повний текст джерелаDong, 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.
Повний текст джерелаChou, 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.
Повний текст джерелаSong, 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.
Повний текст джерелаKiger, 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.
Повний текст джерелаLarosa, 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.
Повний текст джерелаZeng, 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.
Повний текст джерелаGriesbach, 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.
Повний текст джерелаQingsen, 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.
Повний текст джерелаЗвіти організацій з теми "Pressurized Condition"
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.
Повний текст джерелаMohanty, 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.
Повний текст джерела