Relevant bibliographies by topics / Cooled water

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Cooled water'

Author: Grafiati
Published: 4 June 2021
Last updated: 17 February 2022

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Journal articles on the topic "Cooled water"

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Kettleborough, C. F., D. G. Waugaman, and M. Johnson. "The Thermal Performance of the Cross-Flow Three-Dimensional Flat Plate Indirect Evaporative Cooler." Journal of Energy Resources Technology 114, no. 3 (September 1, 1992): 181–86. http://dx.doi.org/10.1115/1.2905939.

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Evaporative coolers consist of two main types: (a) the direct evaporative cooler in which water mixes with the air to be cooled; and (b) the indirect evaporative cooler in which water is sprayed into alternate passages cooling the secondary airflow, which in turns cools the primary flow which then passes to the building to be cooled. A three-dimensional numerical evaluation of the indirect cooler is given. Energy and mass balance equations are derived for the primary and secondary flows and the effectiveness is calculated for different variable inlet velocities and compared with experimental values.
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Usmonov, N., Sh Sanayev, and Z. Yusupov. "CALCULATION OF TEMPERATURE OF ROUTINE WATER COOLED IN IRRIGATED LAYERS." Technical science and innovation 2019, no. 3 (September 18, 2019): 249–55. http://dx.doi.org/10.51346/tstu-01.19.3.-77-0036.

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The article describes the developed mathematical model, algorithm and program for calculating the process of cooling the water leaving the evaporative cooler and the final temperature of humid air. The compilation of a mathematical model is based on the analysis of literature data. Practically at all industrial enterprises, technological equipment is cooled by means of circulating water supply systems equipped with evaporative coolers. The article made a choice of a cooling system for air conditioning systems of residential premises. The developed basic design scheme of the evaporative water and air cooler with the irrigated layer is presented, as well as the estimated thermal and material balance. One of the main elements of these devices is a heat-mass transfer nozzle - sprinkler. This article presents the results of mathematical modeling of processes occurring in the volume of the sprinkler evaporator chamber, Raschig rings composed of vertical polymeric materials. Expressions are obtained for determining the values of air temperature based on the calculation of thermal modeling of the process of cooling circulating water in evaporative coolers of the type in question.
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Dumont, G., Ph Fontaine Vive Roux, and B. Righini. "Water-cooled electronics." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 440, no. 1 (January 2000): 213–23. http://dx.doi.org/10.1016/s0168-9002(99)00880-3.

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Kim, Hak Min, and Jeong Kuk Yeom. "Numerical Model for Water-Cooled EGR Cooler Performance Improvement." Transactions of the Korean Society of Mechanical Engineers - B 44, no. 1 (January 31, 2020): 61–67. http://dx.doi.org/10.3795/ksme-b.2020.44.1.061.

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J,, Venkatesan, Nagarajan G, Seeniraj R. V, and Kumar S. "Mathematical Modeling of Water Cooled Automotive Air Compressor." International Journal of Engineering and Technology 1, no. 1 (2009): 50–56. http://dx.doi.org/10.7763/ijet.2009.v1.9.

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Cai, Jiejin, Claude Renault, and Junli Gou. "Supercritical Water-Cooled Reactors." Science and Technology of Nuclear Installations 2014 (2014): 1–2. http://dx.doi.org/10.1155/2014/548672.

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Kirillov, P. L. "Supercritical water cooled reactors." Thermal Engineering 55, no. 5 (May 2008): 361–64. http://dx.doi.org/10.1134/s0040601508050017.

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Chambers, Jerre Kelly, and Marvin Lawrence Talansky. "AUTOMATED WATER CONTROL FOR WATER COOLED LASERS." Ophthalmic Surgery, Lasers and Imaging Retina 19, no. 2 (February 1988): 142–43. http://dx.doi.org/10.3928/1542-8877-19880201-19.

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Kolhe, Mohan, Du Bin, and Eric Hu. "Water Cooled Concentrated Photovoltaic System." International Journal of Smart Grid and Clean Energy 2, no. 2 (2013): 159–63. http://dx.doi.org/10.12720/sgce.2.2.159-163.

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Schulenberg, T., J. Starflinger, P. Marsault, D. Bittermann, C. Maráczy, E. Laurien, J. A. Lycklama à Nijeholt, et al. "European supercritical water cooled reactor." Nuclear Engineering and Design 241, no. 9 (September 2011): 3505–13. http://dx.doi.org/10.1016/j.nucengdes.2010.09.039.

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Dissertations / Theses on the topic "Cooled water"

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Zhao, Jiyun Ph D. Massachusetts Institute of Technology. "Stability analysis of supercritical water cooled reactors." Thesis, Massachusetts Institute of Technology, 2005. http://hdl.handle.net/1721.1/34651.

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Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005.
Includes bibliographical references (p. 269-277).
The Supercritical Water-Cooled Reactor (SCWR) is a concept for an advanced reactor that will operate at high pressure (25MPa) and high temperature (500°C average core exit). The high coolant temperature as it leaves the reactor core gives the SCWR the potential for high thermal efficiency (45%). However, near the supercritical thermodynamic point, coolant density is very sensitive to temperature which raises concerns about instabilities in the supercritical water-cooled nuclear reactors. To ensure a proper design of SCWR without instability problems, the U.S. reference SCWR design was investigated. The objectives of this work are: (1) to develop a methodology for stability assessment of both thermal-hydraulic and nuclear-coupled stabilities under supercritical pressure conditions, (2) to compare the stability of the proposed SCWR to that of the BWR, and (3) to develop guidance for SCWR designers to avoid instabilities with large margins. Two kinds of instabilities, namely Ledinegg-type flow excursion and Density Wave Oscillations (DWO), have been studied. The DWO analysis was conducted for three oscillation modes: Single channel thermal-hydraulic stability, Coupled-nuclear Out-of-Phase stability and Coupled-nuclear In-Phase stability.
(cont.) Although the supercritical water does not experience phase change, the thermodynamic properties exhibit boiling-like drastic changes around some pseudo-saturation temperature. A three-region model consisting of a heavy fluid region, a heavy-light fluid mixture region and a light fluid region has been used to simulate the supercritical coolant flowing through the core. New non-dimensional governing parameters, namely, the Expansion Number (Nexp) and the Pseudo-Subcooling Number (Npsub) have been identified. A stability map that defines the onset of DWO instabilities has been constructed in the Nexp-Npsu,b plane based on a frequency domain method. It has been found that the U.S. reference SCWR will be stable at full power operating condition with large margin once the proper inlet orifices are chosen. Although the SCWR operates in the supercritical pressure region at steady state, operation at subcritical pressure will occur during a sliding pressure startup process. At subcritical pressure, the stability maps have been developed based on the traditional Subcooling Number and Phase Change Number (also called as Zuber Number). The sensitivity of stability boundaries to different two phase flow models has been studied.
(cont.) It has been found that the Homogcnouls-Nonequilibrium model (HNEM) yields more conservative results at high subcooling numbers while the Homogenous Equilibrium (HEM) model is more conservative at low subcooling numbers. Based on the stability map, a stable sliding pressure startup procedure has been suggested for the U.S. reference SCWR design. To evaluate the stability performance of the U.S. reference SCWR design, comparisons with a typical BWR (Peach Bottom ) have been conducted. Models for BWR stability analysis (Single channel, Coupled-nuclear In-Phase and Out-of-Phase) have been constructed. It is found that, although the SCWR can be stable by proper inlet orificing, it is more sensitive to operating parameters. such as power and flow rate, than a typical BWR. To validate the models developed for both the SCWR and BWR stability analysis, the analytical results were compared with experimental data. The Peach Bottom 2 stability tests were chosen to evaluate the coupled-nuclear stability analysis model. It was found that the analytical model matched the experiment reasonably well for both the oscillation decay ratios and frequencies. Also, the analytical model predicts the same stability trends as the experiment results.
(cont.) Although there arc plenty of tests available for model evaluations at subcritical pressure, the tests at supercritical pressure are very limited. The only test publicly found was for the single channel stability mode. It was found that the three-region model predicts reasonable results compared with the limited test data.
by Jiyun Zhao.
Ph.D.
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Ellis, Colleen Laverna, and Allan D. Kraus. "Preliminary design of a water cooled avionics rack." Thesis, Monterey, California: Naval Postgraduate School, 1993. http://hdl.handle.net/10945/24217.

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Johnson, Kyle D. "High Performance Fuels for Water-Cooled Reactor Systems." Doctoral thesis, KTH, Reaktorfysik, 2016. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-201604.

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Investigation of nitride fuels and their properties has, for decades, been propelled on the basis of their desirable high metal densities and high thermal conductivities, both of which oer intrinsic advantages to performance, economy, and safety in fast and light water reactor systems. In this time several key obstacles have been identied as impeding the implementation of these fuels for commercial applications; namely chemical interactions with air and steam, the noted diculty in sintering of the material, and the high costs associated with the enrichment of 15N. The combination of these limitations, historically, led to the well founded conclusion that the most appropriate use of nitride fuels was in the fast reactor fuel cycle, where the cost burdens associated with them is substantially less. Indeed, it is within this context that the vast majority of work on nitrides has been and continues to be done. Nevertheless, following the 2011 Fukushima-Daiichi nuclear accident, a concerted governmental-industrial eort was embarked upon to explore the alternatives of so-called \accident tolerant" and \high performance" fuels. These fuels would, at the same time, improve the response of the fuel-clad system to severe accidents and improve the economy of operation for light water reactor systems. Among the various candidates proposed are uranium nitride, uranium silicide, and a third \uranium nitride-silicide" composite featuring a mixture of the former. In this thesis a method has been established for the synthesis, fabrication, and characterization of high purity uranium nitride, and uranium nitride-silicide composites, prepared by the spark plasma sintering (SPS) technique. A specic result has been to isolate the impact of the processing parameters on the microstructure of representative fuel pellets, essentially permitting any conceivable microstructure of interest to be fabricated. This has enabled the development of a highly reproducible technique for the production of pellets with microstructures tailored towards any desired porosity between 88-99.9%TD, any grain size between 6-24 μm, and, in the case of  the uranium nitride-silicide composite, a silicide-coated UN matrix. This has permitted the evaluation of these microstructural characteristics on the performance of these materials, specically with respect to their role as accident tolerant fuels. This has generated results which have tightly coupled nitride performance with pellet microstructure, with important implications for the use of nitrides in water-cooled reactors.
Under artionden har forskning om nitridbranseln och dess egenskaper bedrivits pa grundval av nitridbransletsatravarda egenskaper avseende dess hoga metall tathet och hog varmeledningsformaga. Dessa egenskaper besitter vasentliga fordelar avseende prestanda, ekonomi och sakerhet for metallkylda som lattvatten reaktorer. Genom forskning har aven centrala begr ansningar identierats for implementering av nitridbranslen for kommersiellt bruk. Begransningar avser den kemiska interaktionen med luft och vattenanga, en uppmarksammad svarighet att sintring av materialet samt hoga kostnader forknippade med den nodvandiga anrikningen av 15-N. Kombinationen av dessa begransningar resulterade, tidigare, i en valgrundad slutsats att nitridbranslet mest andamalsenliga anvandningsomrade var i karnbranslecykeln for snabba reaktorer. Detta da kostnaderna forenade med implementeringen av branslet ar avsevart lagre. Inom detta sammanhang har majoriteten av forskning avseende nitrider bedrivits och fortskrider an idag. Dock, efter karnkraftsolyckan i Fukushima-Daiichi 2011, inleddes en samlad industriell och statlig anstrangning for att undersoka alternativ till sa kallade \olyckstoleranta" och \hogpresterande" branslen. Dessa branslen skulle samtidigt forbattra reaktionstiden for bransleinkapsling systemet mot allvarliga olyckor samt forbattra driftsekonomin av lattvattenreaktorer. Foreslagna kandidater ar urannitrid, uransilicid och en tredje \uran nitrid-silicid", komposit bestaende av en blandning av de foregaende. Genom denna avhandling har en metod faststallts for syntes, tillverkning och karaktarisering av uran nitrid av hog renhet samt uran nitrid-silicid kompositer, forberedda med tekniken SPS (Spark Plasma Sintering). Ett specikt resultat har varit att isolera eekten av processparametrar pa mikrostrukturen pa representativa branslekutsar. Detta mojliggor, i princip, framstallningen av alla tankbara mikrostrukturer utav intresse for tillverkning. Vidare har detta mojliggjort utvecklingen av en hogeligen reproducerbar  teknik for framstallningen av branslekutsar med mikrostrukturer skraddarsydda for onskad porositet mellan 88 och 99.9 % TD, och kornstorlek mellan 6 och 24 μm. Dartill har en metod for att belagga en matris av uran nitrid-silicid framarbetats. Detta har mojliggjort utvarderingen av dessa mikrostrukturella parametrars paverkan pa materialens prestanda, sarskilt avseende dess roll som olyckstoleranta branslen. Detta har genererat resultat som ar tatt sammanlankat nitridbranslets prestanda till kutsens mikrostruktur, med viktiga konsekvenser for den potentiella anvandningen av nitrider i lattvatten reaktorer.

QC 20170210

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Tan, Yuk Wei. "Development of a small-scale absorption cooled water chiller." Thesis, Nottingham Trent University, 2000. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.324572.

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Hwang, Jyh-Tzong. "Experimental evaluation of a passive water cooled containment concept." Thesis, Massachusetts Institute of Technology, 1994. http://hdl.handle.net/1721.1/28127.

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Fly, Ashley. "Thermal and water management of evaporatively cooled fuel cell vehicles." Thesis, Loughborough University, 2015. https://dspace.lboro.ac.uk/2134/19484.

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Proton Exchange Membrane Fuel Cells (PEMFCs) present a promising alternative to the conventional internal combustion engine for automotive applications because of zero harmful exhaust emissions, fast refuelling times and possibility to be powered by hydrogen generated through renewable energy. However, several issues need to be addressed before the widespread adoption of PEMFCs, one such problem is the removal of waste heat from the fuel cell electrochemical reaction at high ambient temperatures. Automotive scale fuel cells are most commonly liquid cooled, evaporative cooling is an alternative cooling method where liquid water is added directly into the fuel cell flow channels. The liquid water evaporates within the flow channel, both cooling and humidifying the cell. The evaporated water, along with some of the product water, is then condensed from the fuel cell exhaust, stored, and re-used in cooling the fuel cell. This work produces a system level model of an evaporatively cooled fuel cell vehicle suitable for the study of water balance and heat exchanger requirements across steady state operation and transient drive cycles. Modelling results demonstrate the ability of evaporatively cooled fuel cells to self regulate temperature within a narrow region (±2°C) across a wide operating range, provided humidity is maintained within the flow channels through sufficient liquid water addition. The heat exchanger requirements to maintain a self sufficient water supply are investigated, demonstrating that overall heat exchange area can be reduced up to 40% compared to a liquid cooled system due to the presence of phase change within the vehicle radiator improving heat transfer coefficients. For evaporative cooling to remain beneficial in terms of heat exchange area, over 90% of the condensed liquid water needs to be extracted from the exhaust stream. Experimental tests are conducted to investigate the condensation of water vapour from a saturated air stream in a compact plate heat exchanger with chevron flow enhancements. Thermocouples placed within the condensing flow allow the local heat transfer coefficient to be determined and an empirical correlation obtained. The corresponding correlation is used to produce a heat exchanger model and study the influence different heat exchanger layouts have on the overall required heat transfer area for an evaporatively cooled fuel cell vehicle. A one-dimensional, non-isothermal model is also developed to study the distribution of species, current density and temperature along the flow channel of an evaporatively cooled fuel cell using different methods of liquid water addition. Results show that good performance can be achieved with cathode inlet humidities as low as 20%, although some anode liquid water addition may be required at high current densities due to increased electro-osmotic drag. It is also demonstrated that both good membrane hydration and temperature regulation can be managed by uniform addition of liquid water across the cell to maintain a target exhaust relative humidity.
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Chan, Ping-lam. "Development of a simulation model for PWR reactor coolant system /." [Hong Kong] : University of Hong Kong, 1989. http://sunzi.lib.hku.hk/hkuto/record.jsp?B1273617X.

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Fischer, Kai. "Design of a supercritical water cooled reactor pressure vessel and internals /." Karlsruhe : Forschungszentrum Karlsruhe, 2008. http://d-nb.info/991370759/34.

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Gelbart, W., R. R. Johnson, B. Abeysekera, L. Matei, and D. Niculae. "All-Metal water target with spherical window." Helmholtz-Zentrum Dresden - Rossendorf, 2015. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-165885.

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Introduction The use of a prefabricated target window assembly greatly simplifies the window installation. The window module is sealed by metal knife-edges, thus eliminating any elestomers in the target construction. Spherical Havar window offers high strength at reduced thickness and does not require helium cooling. The target body is of platinum-plated silver. The target assembly includes an integral beam collimator and a four-sector mask.
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Xiao, Ruiyang. "The freezing of highly sub-cooled H₂O/D₂O droplets." Columbus, Ohio : Ohio State University, 2008. http://rave.ohiolink.edu/etdc/view?acc%5Fnum=osu1211567463.

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Books on the topic "Cooled water"

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Raven, Greg. Water-cooled VW performance handbook. 3rd ed. St. Paul, Minn: Motorbooks, 2011.

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Mori, Hideo, and Yoshiaki Oka. Supercritical-pressure light water cooled reactors. Tokyo]: Springer, 2014.

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Oka, Yoshiaki, and Hideo Mori, eds. Supercritical-Pressure Light Water Cooled Reactors. Tokyo: Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-55025-9.

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Ellis, Colleen Laverna. Preliminary design of a water cooled avionics rack. Monterey, Calif: Naval Postgraduate School, 1993.

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Kveton, O. K. ITER ISS system alternative specification study revision 1.0. Mississauga, Ont: Canadian Fusion Fuels Technology Project, 1990.

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Ross, W. E. Thermosyphoning analysis with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactor design. Mississauga, Ont: CFFTP, 1994.

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Ross, W. E. Analysis of loss of electrical power with the CATHENA model of the blanket & first wall cooling loop for the SEAFP reactordesign. Mississauga, Ont: CFFTP, 1994.

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Ross, W. E. Modified Cathena Model of a Shield Circuit for ITER. Mississauga, Ont: CFFTP, 1993.

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Kveton, O. K. ITER cooling system: Analysis of heat transfer media, operation and safety of cooling loop and blanket during conditioning and baking. Toronto: Ontario Hydro, 1990.

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Ross, W. E. CATHENA model of shield circuit ITER. Mississauga, Ont: CFFTP, 1992.

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Book chapters on the topic "Cooled water"

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Calabrese, Steven R. "Water Cooled Systems." In Practical Controls, 427–39. New York: River Publishers, 2020. http://dx.doi.org/10.1201/9781003151128-23.

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Toulouevski, Yuri N., and Ilyaz Y. Zinurov. "Water-Cooled Furnace Elements." In Innovation in Electric Arc Furnaces, 215–37. Berlin, Heidelberg: Springer Berlin Heidelberg, 2013. http://dx.doi.org/10.1007/978-3-642-36273-6_12.

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Toulouevski, Yuri N., and Ilyaz Y. Zinurov. "Water-Cooled Furnace Elements." In Innovation in Electric Arc Furnaces, 193–215. Berlin, Heidelberg: Springer Berlin Heidelberg, 2009. http://dx.doi.org/10.1007/978-3-642-03802-0_12.

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Zhang, Xiuping, Lei Jia, Junfeng Wu, Rujin Wang, Jiong Li, and Yu Zhong. "Efficient Water-Cooled Chillers." In Handbook of Energy Systems in Green Buildings, 755–98. Berlin, Heidelberg: Springer Berlin Heidelberg, 2018. http://dx.doi.org/10.1007/978-3-662-49120-1_20.

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Zhang, Xiuping, Lei Jia, Junfeng Wu, Rujin Wang, Jiong Li, and Yu Zhong. "Efficient Water-Cooled Chillers." In Handbook of Energy Systems in Green Buildings, 1–44. Berlin, Heidelberg: Springer Berlin Heidelberg, 2017. http://dx.doi.org/10.1007/978-3-662-49088-4_20-1.

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Ait Saada, Sonia, Idir Kecili, and Rezki Nebbali. "Water-Cooled Photovoltaic Panel Efficiency." In ICREEC 2019, 61–67. Singapore: Springer Singapore, 2020. http://dx.doi.org/10.1007/978-981-15-5444-5_8.

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Dolan, Thomas J. "Pulsed and Water-Cooled Magnets." In Magnetic Fusion Technology, 71–118. London: Springer London, 2013. http://dx.doi.org/10.1007/978-1-4471-5556-0_3.

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Tamada, Isao, Yasuhiro Mizuno, Hiroyasu Shimanuki, Takaki Okochi, and Zong Xiumei. "Development of a Water-Cooled Condenser." In Lecture Notes in Electrical Engineering, 591–605. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-8506-2_40.

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Oka, Yoshiaki, and Shinichi Morooka. "Reactor Design and Safety." In Supercritical-Pressure Light Water Cooled Reactors, 21–248. Tokyo: Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-55025-9_2.

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Oka, Yoshiaki. "Introduction and Overview." In Supercritical-Pressure Light Water Cooled Reactors, 1–20. Tokyo: Springer Japan, 2014. http://dx.doi.org/10.1007/978-4-431-55025-9_1.

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Conference papers on the topic "Cooled water"

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Harada, Masaki, Takashi Yasuda, Shota Terachi, Sergio Pujols, and Jason R. Spenny. "Water Cooled Charge Air Cooler Development." In SAE 2016 World Congress and Exhibition. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 2016. http://dx.doi.org/10.4271/2016-01-0651.

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Lee, Kyu Hyun, and Jong Pil Won. "Thermal Analysis of Compact Water Cooled Engine Oil Cooler." In 1995 Vehicle Thermal Management Systems Conference and Exhibition. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 1997. http://dx.doi.org/10.4271/971819.

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Samarkin, Vadim, Alexander Aleksandrov, Valeri Dubikovsky, and Alexis Kudryashov. "Water-cooled bimorph correctors." In 5th International Workshop on Adaptive Optics for Industry and Medicine, edited by Wenhan Jiang. SPIE, 2005. http://dx.doi.org/10.1117/12.669365.

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Chalgren, Robert D., Lawrence Barron, and Daniel R. Bjork. "A Controllable Water Cooled Charge Air Cooler (WCCAC) for Diesel Trucks." In SAE Commercial Vehicle Engineering Congress & Exhibition. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 2004. http://dx.doi.org/10.4271/2004-01-2614.

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Lee, Kyu Hyun, and Jong Pil Won. "Thermal Design of Compact Circular External Water Cooled Engine Oil Cooler." In International Off-Highway & Powerplant Congress & Exposition. 400 Commonwealth Drive, Warrendale, PA, United States: SAE International, 1996. http://dx.doi.org/10.4271/961812.

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Moore, David A., Matt Slaby, Tahir Cader, and Kevin Regimbal. "Hybrid warm water cooled supercomputing system." In 2016 15th IEEE Intersociety Conference on Thermal and Thermomechanical Phenomena in Electronic Systems (ITherm). IEEE, 2016. http://dx.doi.org/10.1109/itherm.2016.7517604.

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Duffey, R., L. K. H. Leung, D. Martin, B. Sur, and M. Yetisir. "A Supercritical Water-Cooled Small Modular Reactor." In ASME 2011 Small Modular Reactors Symposium. ASMEDC, 2011. http://dx.doi.org/10.1115/smr2011-6548.

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A new small modular reactor (SMR) is proposed for a 300 MW(e) nuclear generating station. It is referred as the SuperSafe© Reactor (SSR) and is a scaled down version of the Canadian supercritical water-cooled reactor (SCWR), which is designed to operate at supercritical conditions (pressure of 25 MPa and fluid temperature of 625°C) at the turbine inlet with high cycle efficiencies (∼45%). The supercritical turbine technology and associated components used in the balance of plant (BOP) are similar to those in existing supercritical fossil-fired plants. The reactor core consists of fuel channels, which are submerged in a subcooled heavy-water moderator pool inside a low-pressure calandria vessel. Each fuel channel consists of a pressure tube and a ceramic insulator enclosed inside a porous stainless steel sleeve. The moderator provides cooling to fuel channels under normal operation and postulated accident scenarios. This design feature enables the use of a flash-driven passive moderator cooling — an inherent safety feature of the proposed design. A major safety goal is to achieve a passive “no core melt” configuration for the channels and fuel.
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Aminov, Rashid. "EMERGENCY COOLING SYSTEM FOR WATER-COOLED REACTORS." In 17th International Multidisciplinary Scientific GeoConference SGEM2017. Stef92 Technology, 2017. http://dx.doi.org/10.5593/sgem2017/41/s16.001.

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Aminov, Rashid. "EMERGENCY COOLING SYSTEM FOR WATER-COOLED REACTORS." In 18th International Multidisciplinary Scientific GeoConference SGEM2018. Stef92 Technology, 2018. http://dx.doi.org/10.5593/sgem2018/4.1/s16.002.

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Maughan, Clyde V., and Matthias Svoboda. "Water-cooled stator windings copper oxide issues." In 2016 IEEE Electrical Insulation Conference (EIC). IEEE, 2016. http://dx.doi.org/10.1109/eic.2016.7548654.

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Reports on the topic "Cooled water"

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Dale, Gregory E., Michael Andrew Holloway, and Elias Noel Pulliam. Water Cooled Mirror Design. Office of Scientific and Technical Information (OSTI), March 2015. http://dx.doi.org/10.2172/1177180.

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Chiang, I., J. Geller, C.-I. Pai, C. Pearson, A. Pendzick, and E. Zitvogel. Water-cooled platinum C target. Office of Scientific and Technical Information (OSTI), March 1998. http://dx.doi.org/10.2172/1157477.

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Macdonald, Dgiby, Mirna Urquidi-Macdonald, and Jonathan Pitt. Electrochemistry of Water-Cooled Nuclear Reactors. Office of Scientific and Technical Information (OSTI), August 2006. http://dx.doi.org/10.2172/890516.

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Forsberg, C. (Advanced technologies for water-cooled reactors). Office of Scientific and Technical Information (OSTI), July 1988. http://dx.doi.org/10.2172/6888806.

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Pimblott, S. M. Effects of Water Radiolysis in Water Cooled Reactors. Technical progress report. Office of Scientific and Technical Information (OSTI), January 2000. http://dx.doi.org/10.2172/761635.

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Thompson, M. W. Boundry description for removal of water cooled chillers. Office of Scientific and Technical Information (OSTI), December 1995. http://dx.doi.org/10.2172/10103106.

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Author, Not Given. Advanced water-cooled phosphoric acid fuel cell development. Office of Scientific and Technical Information (OSTI), January 1992. http://dx.doi.org/10.2172/7039349.

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T. R. Allen and G. S. Was. Candidate Materials Evaluation for Supercritical Water-Cooled Reactor. Office of Scientific and Technical Information (OSTI), December 2008. http://dx.doi.org/10.2172/944040.

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Pimblott, S. M. Effects of Water Radiolysis in Water Cooled Reactors, ''NERI Proposal No.99-001C''. Office of Scientific and Technical Information (OSTI), October 1999. http://dx.doi.org/10.2172/762090.

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Pimblott, S. M. Effects of Water Radiolysis in Water Cooled Reactors, NERI Proposal No.99-0010. Office of Scientific and Technical Information (OSTI), August 2000. http://dx.doi.org/10.2172/761538.

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You might also be interested in the extended bibliographies on the topic 'Cooled water' for particular source types:
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