Artigos de revistas sobre o tema "Nuclear boiling"
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Wilczek, Frank. "Nuclear and subnuclear boiling". Nature 395, n.º 6699 (setembro de 1998): 220–21. http://dx.doi.org/10.1038/26107.
Texto completo da fonteGuo, Zhong De, e Shu Fang Zhang. "The Pure Heat Conversion Coefficient Analysis Method for Thermodynamic System of Advance Boiling Water Reactor Nuclear Power Unit". Advanced Materials Research 383-390 (novembro de 2011): 6514–18. http://dx.doi.org/10.4028/www.scientific.net/amr.383-390.6514.
Texto completo da fonteGiustini, Giovanni. "Modelling of Boiling Flows for Nuclear Thermal Hydraulics Applications—A Brief Review". Inventions 5, n.º 3 (14 de setembro de 2020): 47. http://dx.doi.org/10.3390/inventions5030047.
Texto completo da fonteKim, Kang Seog, Andrew Ward, Ugur Mertyurek, Mehdi Asgari e William Wieselquist. "Validation of the SCALE/Polaris–PARCS Code Procedure With the ENDF/B-VII.1 AMPX 56-Group Library: Boiling Water Reactor". Journal of Nuclear Engineering 5, n.º 3 (1 de agosto de 2024): 260–73. http://dx.doi.org/10.3390/jne5030018.
Texto completo da fontePodowski, Michael Z., e Raf M. Podowski. "Mechanistic Multidimensional Modeling of Forced Convection Boiling Heat Transfer". Science and Technology of Nuclear Installations 2009 (2009): 1–10. http://dx.doi.org/10.1155/2009/387020.
Texto completo da fonteBang, In Cheol, Jacopo Buongiorno, Lin-Wen Hu e Hsin Wang. "ICONE15-10030 Measurement of Key Pool Boiling Parameters in Nanofluids for Nuclear Applications". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_11.
Texto completo da fonteTõke, Jan. "Boiling Patterns of Iso-asymmetric Nuclear Matter". Journal of Physics: Conference Series 420 (25 de março de 2013): 012100. http://dx.doi.org/10.1088/1742-6596/420/1/012100.
Texto completo da fonteStojanovic, Andrijana, Srdjan Belosevic, Nenad Crnomarkovic, Ivan Tomanovic e Aleksandar Milicevic. "Nucleate pool boiling heat transfer: Review of models and bubble dynamics parameters". Thermal Science, n.º 00 (2021): 69. http://dx.doi.org/10.2298/tsci200111069s.
Texto completo da fonteBaldwin, Michael, Andre LeClair, Alok Majumdar, Jason Hartwig, Vishwanath Ganesan e Issam Mudawar. "Modeling of cryogenic heated-tube flow boiling experiments of nitrogen and methane with Generalized Fluid System Simulation Program". IOP Conference Series: Materials Science and Engineering 1301, n.º 1 (1 de maio de 2024): 012158. http://dx.doi.org/10.1088/1757-899x/1301/1/012158.
Texto completo da fonteKurskii, A. S., V. M. Eshcherkin, V. V. Kalygin, M. N. Svyatkin e I. I. Semidotskii. "Boiling water vessel reactors for nuclear district heating". Atomic Energy 111, n.º 5 (19 de fevereiro de 2012): 370–76. http://dx.doi.org/10.1007/s10512-012-9506-9.
Texto completo da fonteNguyen, Ngoc Dat, e Van Thai Nguyen. "Performance Comparison of ANN-Based Model and Empirical Correlations for Void Fraction Prediction of Subcooled Boiling Flow in Vertical Upward Channel". Nuclear Science and Technology 11, n.º 4 (13 de janeiro de 2023): 07–18. http://dx.doi.org/10.53747/nst.v11i4.335.
Texto completo da fonteTieszen, S., H. Merte, V. S. Arpaci e S. Selamoglu. "Crevice Boiling in Steam Generators". Journal of Heat Transfer 109, n.º 3 (1 de agosto de 1987): 761–67. http://dx.doi.org/10.1115/1.3248155.
Texto completo da fonteYang, X., S. Y. Jiang e Y. Zhang. "Experimental and numerical investigation of sub-cooled boiling, condensation, and void flashing in nuclear heating reactor test loop". Kerntechnik 67, n.º 2-3 (1 de abril de 2002): 90–94. http://dx.doi.org/10.1515/kern-2002-0041.
Texto completo da fonteKunugi, Tomoaki, e Yasuo Ose. "Direct Numerical Simulation and Visualization of Subcooled Pool Boiling". Science and Technology of Nuclear Installations 2014 (2014): 1–11. http://dx.doi.org/10.1155/2014/120604.
Texto completo da fonteCho, A. "NUCLEAR PHYSICS: Scheme for Boiling Nuclear Matter Gathers Steam at Accelerator Lab". Science 312, n.º 5771 (14 de abril de 2006): 190–91. http://dx.doi.org/10.1126/science.312.5771.190.
Texto completo da fonteMukherjee, Sayantan, Shikha Ebrahim, Purna Chandra Mishra, Naser Ali e Paritosh Chaudhuri. "A Review on Pool and Flow Boiling Enhancement Using Nanofluids: Nuclear Reactor Application". Processes 10, n.º 1 (17 de janeiro de 2022): 177. http://dx.doi.org/10.3390/pr10010177.
Texto completo da fonteRefaey, A. M., S. Elnaggar, S. H. Abdel-Latif e A. Hamza. "The effect of surfactant concentrations and surface material on heat transfer coefficient in nucleate boiling regime". Kerntechnik 86, n.º 5 (1 de outubro de 2021): 365–74. http://dx.doi.org/10.1515/kern-2020-0064.
Texto completo da fonteMa, Xiaojing, e Ping Cheng. "Numerical Simulation of Complete Pool Boiling Curves: From Nucleation to Critical Heat Flux Through Transition Boiling to Film Boiling". Nuclear Science and Engineering 193, n.º 1-2 (6 de setembro de 2018): 1–13. http://dx.doi.org/10.1080/00295639.2018.1504566.
Texto completo da fonteSATO, ITARU, JUN SASAKI, HIROSHI SATOH e KEIJI OKADA. "Effects of Treatment Time and Thickness of Meat on the Removal of Radioactive Cesium from Beef Slices by Boiling and Water Extraction". Journal of Food Protection 82, n.º 4 (26 de março de 2019): 623–27. http://dx.doi.org/10.4315/0362-028x.jfp-18-427.
Texto completo da fonteChiang, Ren-Tai. "Overview on Steady-state Nuclear Methods for BWR Nuclear Core Design and Analysis". ASEAN Journal on Science and Technology for Development 35, n.º 3 (24 de dezembro de 2018): 223–27. http://dx.doi.org/10.29037/ajstd.514.
Texto completo da fonteChuang, T. J., e Y. M. Ferng. "Experimentally investigating boiling characteristics in the transition boiling for the downward facing heating". Annals of Nuclear Energy 91 (maio de 2016): 148–55. http://dx.doi.org/10.1016/j.anucene.2016.01.004.
Texto completo da fonteLahaye, Marc, Cyrille Rochas e Wilfred Yaphe. "A new procedure for determining the heterogeneity of agar polymers in the cell walls of Gracilaria spp. (Gracilariaceae, Rhodophyta)". Canadian Journal of Botany 64, n.º 3 (1 de março de 1986): 579–85. http://dx.doi.org/10.1139/b86-074.
Texto completo da fonteSharaievskii, G. "Problems in Validation of the Chornobyl Accident Initiating Event". Nuclear and Radiation Safety, n.º 1(69) (17 de fevereiro de 2016): 20–27. http://dx.doi.org/10.32918/nrs.2016.1(69).03.
Texto completo da fonteBankoff, S. G., e T. E. Rehm. "Convective Boiling in Narrow Concentric Annuli". Journal of Engineering for Gas Turbines and Power 112, n.º 4 (1 de outubro de 1990): 607–13. http://dx.doi.org/10.1115/1.2906213.
Texto completo da fonteDong, Wu-han, Ming Gao, Zhong-xiang Shen e Li-xin Zhang. "Study on boiling heat transfer mechanism based on microlayer evaporation theory". Journal of Physics: Conference Series 2280, n.º 1 (1 de junho de 2022): 012034. http://dx.doi.org/10.1088/1742-6596/2280/1/012034.
Texto completo da fonteLipka, Maciej, Gawel Madejowski, Rafal Prokopowicz e Krzysztof Pytelt. "Approximate model for evaluation of thermal-hydraulic transients associated with rapid power increase in research nuclear reactor". Nuclear Technology and Radiation Protection 35, n.º 4 (2020): 310–15. http://dx.doi.org/10.2298/ntrp2004310l.
Texto completo da fonteJohn, T. M., e O. P. Singh. "Coolant boiling noise in LMFBRs". Annals of Nuclear Energy 12, n.º 1 (janeiro de 1985): 45–47. http://dx.doi.org/10.1016/0306-4549(85)90007-6.
Texto completo da fonteSorokin, V. V. "Boiling and crisis of boiling of a two-phase liquid in spherical microfuel fills". Atomic Energy 106, n.º 1 (janeiro de 2009): 17–25. http://dx.doi.org/10.1007/s10512-009-9125-2.
Texto completo da fonteAvramenko, A. A., A. I. Tyriniv, N. P. Dmitrenko e M. M. Kovetska. "INFLUENCE OF UNSTEADY CONDITIONS ON HEAT EXCHANGE DURING A SHARPY TRANSITION TO FILM BOILING". Thermophysics and Thermal Power Engineering 46, n.º 3 (2 de fevereiro de 2022): 23–32. http://dx.doi.org/10.31472/ttpe.3.2022.2.
Texto completo da fonteBucci, M., M. Zupančič e I. Golobič. "Multi-scale boiling heat transfer investigation on micro-thin aluminum heaters". Journal of Physics: Conference Series 2766, n.º 1 (1 de maio de 2024): 012128. http://dx.doi.org/10.1088/1742-6596/2766/1/012128.
Texto completo da fonteCeceñas-Falcón, Miguel, e Robert M. Edwards. "Stability Monitoring Tests Using a Nuclear-Coupled Boiling Channel Model". Nuclear Technology 131, n.º 1 (julho de 2000): 1–11. http://dx.doi.org/10.13182/nt00-a3100.
Texto completo da fonteVook, R. W., T. V. Rao, T. Swirbel, J. Bucci e W. Meyer. "Thin films for radiation control in boiling water nuclear reactors". Proceedings, annual meeting, Electron Microscopy Society of America 44 (agosto de 1986): 520–21. http://dx.doi.org/10.1017/s0424820100144115.
Texto completo da fonteJaunet, Y., M. Bucci, M. Zupančič, J. Sebilleau, C. Colin e I. Golobič. "Study of nucleate boiling growth regime on thin surfaces." Journal of Physics: Conference Series 2766, n.º 1 (1 de maio de 2024): 012135. http://dx.doi.org/10.1088/1742-6596/2766/1/012135.
Texto completo da fonteQing, Ning, Lawrence D. Colebrook, John T. Edward, Allan Kon e Francis L. Chubb. "Reactions of α-phenylglycinamide with some carbonyl compounds. Formation of 5,7-diisopropyl-8,8-dimethyl-2-oxo-3-phenylimidazolidino-[1,2-c]-tetrahydro-[1,3]-oxazine, and determination of structure and stereochemistry by nuclear Overhauser effect difference measurements". Canadian Journal of Chemistry 67, n.º 10 (1 de outubro de 1989): 1560–64. http://dx.doi.org/10.1139/v89-238.
Texto completo da fonteSchindler, M., e LW Jiang. "Epidermal growth factor and insulin stimulate nuclear pore-mediated macromolecular transport in isolated rat liver nuclei". Journal of Cell Biology 104, n.º 4 (1 de abril de 1987): 849–53. http://dx.doi.org/10.1083/jcb.104.4.849.
Texto completo da fonteAvramova, Maria, e Diana Cuervo. "Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmark Databases". Science and Technology of Nuclear Installations 2013 (2013): 1–12. http://dx.doi.org/10.1155/2013/508485.
Texto completo da fonteFujita, Nobuyuki, e David A. Rice. "Core Boiling During Midloop Operation". Nuclear Technology 93, n.º 1 (janeiro de 1991): 36–46. http://dx.doi.org/10.13182/nt91-a34516.
Texto completo da fonteRahnema, Farzad, Dan Ilas e Shivakumar Sitaraman. "Boiling Water Reactor Benchmark Calculations". Nuclear Technology 117, n.º 2 (fevereiro de 1997): 184–94. http://dx.doi.org/10.13182/nt97-a35324.
Texto completo da fonteMelikhov, Vladimir, Oleg Melikhov, Sergey Yakush e Oleg Konovalov. "Comparative analysis of film boiling correlations for steam explosion problem". E3S Web of Conferences 411 (2023): 01064. http://dx.doi.org/10.1051/e3sconf/202341101064.
Texto completo da fonteMennerdahl, Dennis. "KRITZ-1-Mk CRITICAL MEASUREMENTS AT TEMPERATURES FROM 20 °C TO 250 °C". EPJ Web of Conferences 247 (2021): 09028. http://dx.doi.org/10.1051/epjconf/202124709028.
Texto completo da fonteKozhemyakin, V. V., e N. D. Koshkin. "Evaluation of the possibility of using vapor-liquid injectors in installations with a liquid metal coolant". Transactions of the Krylov State Research Centre S-I, n.º 1 (8 de dezembro de 2021): 169–70. http://dx.doi.org/10.24937/2542-2324-2021-1-s-i-169-170.
Texto completo da fonteRzehak, Roland, e Eckhard Krepper. "CFD for Subcooled Flow Boiling: Parametric Variations". Science and Technology of Nuclear Installations 2013 (2013): 1–22. http://dx.doi.org/10.1155/2013/687494.
Texto completo da fonteARAKI, Hitoshi, Kazuo HAGA e Koichiro NAKAMOTO. "Sodium boiling detection by acoustic method." Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan 28, n.º 2 (1986): 176–84. http://dx.doi.org/10.3327/jaesj.28.176.
Texto completo da fonteChen, X. N., F. Gabrielli, A. Rineiski e T. Schulenberg. "Boiling water cooled travelling wave reactor". Annals of Nuclear Energy 134 (dezembro de 2019): 342–49. http://dx.doi.org/10.1016/j.anucene.2019.06.037.
Texto completo da fonteKim, Seung Jun, Russell C. Johns, Junsoo Yoo e Emilio Baglietto. "Progress Toward Simulating Departure from Nucleate Boiling at High-Pressure Applications with Selected Wall Boiling Closures". Nuclear Science and Engineering 194, n.º 8-9 (4 de maio de 2020): 690–707. http://dx.doi.org/10.1080/00295639.2020.1743579.
Texto completo da fonteKončar, Boštjan, e Borut Mavko. "Simulation of Boiling Flow Experiments Close to CHF with the Neptune_CFD Code". Science and Technology of Nuclear Installations 2008 (2008): 1–8. http://dx.doi.org/10.1155/2008/732158.
Texto completo da fonteMimouni, Stephane, William Benguigui, Solène Fleau, Arnaud Foissac, Mathieu Guingo, Mickael Hassanaly, Jérôme Lavieville et al. "Dispersed Two-Phase Flow Modelling for Nuclear Safety in the NEPTUNE_CFD Code". Science and Technology of Nuclear Installations 2017 (2017): 1–41. http://dx.doi.org/10.1155/2017/3238545.
Texto completo da fonteBang, In-Cheol, e Ji-Hwan Jeong. "NANOTECHNOLOGY FOR ADVANCED NUCLEAR THERMAL-HYDRAULICS AND SAFETY: BOILING AND CONDENSATION". Nuclear Engineering and Technology 43, n.º 3 (25 de junho de 2011): 217–42. http://dx.doi.org/10.5516/net.2011.43.3.217.
Texto completo da fonteGopaL, M., e P. Pratapachandran Nair. "A New Oftimal Control Strategy for a Nuclear Boiling Water Reactor". IEEE Transactions on Nuclear Science 32, n.º 2 (1985): 1180–89. http://dx.doi.org/10.1109/tns.1985.4333572.
Texto completo da fonteRao, T. V., R. W. Vook, W. Meyer e C. Wittwer. "Protective coatings for radiation control in boiling water nuclear power reactors". Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films 5, n.º 4 (julho de 1987): 2701–5. http://dx.doi.org/10.1116/1.574723.
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