Artículos de revistas sobre el tema "Rod in Cross-Flow"
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Tian, W. X., K. Zhang, Y. D. Hou, Y. P. Zhang, S. Z. Qiu y G. H. Su. "Hydrodynamics of two-phase flow in a rod bundle under cross-flow condition". Annals of Nuclear Energy 91 (mayo de 2016): 206–14. http://dx.doi.org/10.1016/j.anucene.2016.01.025.
Texto completoIWAMURA, Takamichi, Hiromichi ADACHI y Makoto SOBAJIMA. "Air-Water Two-Phase Cross Flow Resistance in Rod Bundle". Journal of Nuclear Science and Technology 23, n.º 7 (julio de 1986): 658–60. http://dx.doi.org/10.1080/18811248.1986.9735034.
Texto completoUpnere, Sabine, Normunds Jekabsons, Sergejs Dementjevs y Michael Wohlmuther. "Experimental studies of a single flexibly-mounted rod in a triangular rod bundle in cross-flow". MATEC Web of Conferences 148 (2018): 09002. http://dx.doi.org/10.1051/matecconf/201814809002.
Texto completoOSAKABE, Masahiro. "Pressure Loss of Single-Phase Slanting Cross Flow in Rod Bundle". Journal of Nuclear Science and Technology 24, n.º 6 (junio de 1987): 498–500. http://dx.doi.org/10.1080/18811248.1987.9735835.
Texto completoZhang, Weizhong, Hiroyuki Yoshida, Yasuo Ose, Akira Ohnuki, Hajime Akimoto, Akitoshi Hotta y Ken Fujimura. "ICONE15-10082 NUMERICAL INVESTIGATION OF CROSS FLOW PHENOMENA IN A TIGHT-LATTICE ROD BUNDLE USING ADVANCED INTERFACE TRACKING METHOD". Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_35.
Texto completoZHANG, Weizhong, Hiroyuki YOSHIDA, Yasuo OSE, Akira OHNUKI y Hajime AKIMOTO. "0612 Statistical Evaluation of Cross Flow in a Tight-lattice Rod Bundle". Proceedings of the JSME annual meeting 2007.3 (2007): 145–46. http://dx.doi.org/10.1299/jsmemecjo.2007.3.0_145.
Texto completoOsakabe, M. y H. Futamata. "Effect of inserted rod and cross flow on top flooding of pipe". International Journal of Multiphase Flow 22, n.º 5 (septiembre de 1996): 883–91. http://dx.doi.org/10.1016/0301-9322(96)00032-8.
Texto completoPakhomov, A. A., E. A. Khodyakov, V. S. Bocharnikov, V. G. Grin, N. A. Kolobanova y E. S. Vorontsova. "Theoretical substantiation of the principle of operation of the rod flow meter of irrigation canals". IOP Conference Series: Earth and Environmental Science 965, n.º 1 (1 de enero de 2022): 012006. http://dx.doi.org/10.1088/1755-1315/965/1/012006.
Texto completoHIGUCHI, Tatsuya, Shinji MATSUNAGA, Michio SADATOMI y Akimaro KAWAHARA. "F42 Two-Phase Diversion Cross-Flow between Triangle Tight Lattice Rod Bundle Subchannels". Proceedings of Conference of Kyushu Branch 2007.60 (2007): 219–20. http://dx.doi.org/10.1299/jsmekyushu.2007.60.219.
Texto completoMORI, Naoki, Syouhei KIYOSAKI, Akimaro KAWAHARA y Michio SADATOMI. "2622 Study on Diversion Cross-Flow in a Channel Simplifying BWR Rod Bundle". Proceedings of the JSME annual meeting 2006.3 (2006): 1–2. http://dx.doi.org/10.1299/jsmemecjo.2006.3.0_1.
Texto completoSeo, Ye-Bon, SalaiSargunan S. Paramanantham, Jin-Yeong Bak, Byongjo Yun y Warn-Gyu Park. "CFD Analysis of Subcooled Flow Boiling in 4 × 4 Rod Bundle". Applied Sciences 10, n.º 13 (30 de junio de 2020): 4559. http://dx.doi.org/10.3390/app10134559.
Texto completoChang, Chao Cheng y Yao Sheng Hsiao. "Effect of Grain Size on Cross Wedge Rolling of Micro Copper Rod". Key Engineering Materials 622-623 (septiembre de 2014): 905–11. http://dx.doi.org/10.4028/www.scientific.net/kem.622-623.905.
Texto completoKenzhegulov, B. Z., S. B. Kenzhegulova, D. B. Alibiyev y A. Sh Kazhikenova. "Finite element modeling of heat propagation of a complete rod of constant cross-section". Bulletin of the Karaganda University. "Physics" Series 108, n.º 4 (30 de diciembre de 2022): 94–105. http://dx.doi.org/10.31489/2022ph4/94-105.
Texto completoMishchenko, Andrey V. "Stationary temperature field in multi-layered rods with discontinuous of cross section width". Vestnik MGSU, n.º 1 (enero de 2019): 12–21. http://dx.doi.org/10.22227/1997-0935.2019.1.12-21.
Texto completoKUDO, Hiroyuki, Shinji MATSUNAGA, Tatsuya HIGUCHI, Akimaro KAWAHARA y Michio SADATOMI. "2623 Two-phase Diversion Cross-Flow between Triangle Tight Lattice Rod Bundle Subchannels : Experiment and analysis of flow redistribution". Proceedings of the JSME annual meeting 2006.3 (2006): 3–4. http://dx.doi.org/10.1299/jsmemecjo.2006.3.0_3.
Texto completoYull Suh, Kune y Neil E. Todreas. "An Experimental Correlation of Cross-Flow Pressure Drop for Triangular Array Wire-Wrapped Rod Assemblies". Nuclear Technology 76, n.º 2 (febrero de 1987): 229–40. http://dx.doi.org/10.13182/nt87-a33877.
Texto completoTanaka, Takaaki, Kensuke Usui, Kenji Kouda y Kazuhiro Nakanishi. "Filtration Behaviors of Rod-Shaped Bacterial Broths in Unsteady-State Phase of Cross-Flow Filtration." JOURNAL OF CHEMICAL ENGINEERING OF JAPAN 29, n.º 6 (1996): 973–81. http://dx.doi.org/10.1252/jcej.29.973.
Texto completoMoorthi, A. y Anil Kumar Sharma. "Investigation of cross flow mixing on rod bundle safety margins using sub-channel analysis framework". Nuclear Engineering and Design 335 (agosto de 2018): 30–43. http://dx.doi.org/10.1016/j.nucengdes.2018.04.026.
Texto completoAkhmetov, Sayranbek, Anarbay Kudaykulov y Dossan Bizhanov. "Determination of thermally stressed state of rod elements of variable cross section under the impact of a lateral heat flow, heat exchange and surface thermal insulation". E3S Web of Conferences 216 (2020): 01073. http://dx.doi.org/10.1051/e3sconf/202021601073.
Texto completoMatozinhos, Camila F., Gabriel C. Q. Tomaz, Thien Nguyen y Yassin Hassan. "Experimental investigation of turbulent flow characteristics in cross-flow planes of a 5×5 rod bundle with a spacer grid". International Journal of Heat and Fluid Flow 87 (febrero de 2021): 108757. http://dx.doi.org/10.1016/j.ijheatfluidflow.2020.108757.
Texto completoBerdnikov, Vladimir, Konstantin Mitin y Alina Mitina. "Influence Of Relative Size Of The U-Shaped Silicon Rod On Conjugate Heat Transfer In The Regime Of Gas Buayancy Induced Convection". Siberian Journal of Physics 10, n.º 3 (1 de octubre de 2015): 76–88. http://dx.doi.org/10.54362/1818-7919-2015-10-3-76-88.
Texto completoLiu, Bao Jun, Jing Yu Dong, Cheng Ting Liu, Li Ping Guo, Yin Peng Li y Wu Yi Shan. "Coherent and Co-Current Flow Separator Optimized Experiment". Applied Mechanics and Materials 529 (junio de 2014): 202–6. http://dx.doi.org/10.4028/www.scientific.net/amm.529.202.
Texto completoKAWAHARA, Akimaro, Tatsuya HIGUCHI, Michio SADATOMI y Hiroyuki KUDO. "Single- and Two-Phase Diversion Cross-Flows Between Triangle Tight Lattice Rod Bundle Subchannels -Data on Flow Resistance and Interfacial Friction Coefficients for the Cross-Flow". Journal of Power and Energy Systems 1, n.º 1 (2007): 111–22. http://dx.doi.org/10.1299/jpes.1.111.
Texto completoZHANG, Weizhong, Hiroyuki YOSHIDA, Yasuo OSE, Akira OHNUKI, Hajime AKIMOTO, Akitoshi HOTTA y Ken FUJIMURA. "OS10-9 Study on Cross Flow Phenomena in a Tight-lattice Rod Bundle by Statistical Method". Proceedings of the National Symposium on Power and Energy Systems 2007.12 (2007): 85–88. http://dx.doi.org/10.1299/jsmepes.2007.12.85.
Texto completoQu, Wenhai, Jinbiao Xiong, Shilong Chen y Xu Cheng. "High-fidelity PIV measurement of cross flow in 5 × 5 rod bundle with mixing vane grids". Nuclear Engineering and Design 344 (abril de 2019): 131–43. http://dx.doi.org/10.1016/j.nucengdes.2019.01.021.
Texto completoPramuditya, Syeilendra, Minoru Takahashi y Hisashi Ninokata. "Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wire". Annals of Nuclear Energy 87 (enero de 2016): 803–16. http://dx.doi.org/10.1016/j.anucene.2014.06.053.
Texto completoGad-el-Hak, Ibrahim, Njuki Mureithi, Kostas Karazis y Gary Williams. "Jet cross-flow induced vibrations in rod bundles. Part II: Transverse vibration results and excitation mechanisms". Nuclear Engineering and Design 400 (diciembre de 2022): 112044. http://dx.doi.org/10.1016/j.nucengdes.2022.112044.
Texto completoZhang, K., Y. D. Hou, W. X. Tian, Y. P. Zhang, G. H. Su y S. Z. Qiu. "Experimental investigation on steam-water two-phase flow boiling heat transfer in a staggered horizontal rod bundle under cross-flow condition". Experimental Thermal and Fluid Science 96 (septiembre de 2018): 192–204. http://dx.doi.org/10.1016/j.expthermflusci.2018.03.009.
Texto completoSargeni, A. y E. Ivanov. "AN IRSN CONTRIBUTION TO THE UAM PROJECT: THERMAL-HYDRAULIC AND NEUTRONIC UNCERTAINTIES PROPAGATION IN A ROD EJECTION, FIRST RESULTS". EPJ Web of Conferences 247 (2021): 07003. http://dx.doi.org/10.1051/epjconf/202124707003.
Texto completoKAWAHARA, Akimaro, Tatsuya Higuchi, Hiroyuki KUDOU y Michio SADATOMI. "OS8-1 Single- and Two-Phase Diversion Cross-Flows between Triangle Tight Lattice Rod Bundle Subchannels : Data on Flow Resistance and Interfacial Friction Coefficients for the Cross-Flow". Proceedings of the National Symposium on Power and Energy Systems 2006.11 (2006): 203–4. http://dx.doi.org/10.1299/jsmepes.2006.11.203.
Texto completoKennedy, Kevin F. "An Approximate Three-Dimensional Metal Flow Analysis for Shape Rolling". Journal of Engineering for Industry 110, n.º 3 (1 de agosto de 1988): 223–31. http://dx.doi.org/10.1115/1.3187873.
Texto completoMORIMATSU, Yuki, Michio SADATOMI y Akimaro KAWAHARA. "B22 Experiment and Analysis of Two-Phase Diversion Cross-Flow between Triangle Tight Lattice Rod Bundle Subchannels". Proceedings of Conference of Kyushu Branch 2008.61 (2008): 45–46. http://dx.doi.org/10.1299/jsmekyushu.2008.61.45.
Texto completoNader, A. "Magnetic flux diffusion inside a superconducting long rod with square cross section in the flux-flow regime". Physica B: Condensed Matter 321, n.º 1-4 (agosto de 2002): 365–67. http://dx.doi.org/10.1016/s0921-4526(02)01076-1.
Texto completoZHANG, Weizhong, Hiroyuki YOSHIDA, Yasuo OSE, Akira OHNUKI, Hajime AKIMOTO, Akitoshi HOTTA y Ken FUJIMURA. "Numerical Investigation of Cross Flow Phenomena in a Tight-Lattice Rod Bundle Using Advanced Interface Tracking Method". Journal of Power and Energy Systems 2, n.º 2 (2008): 456–66. http://dx.doi.org/10.1299/jpes.2.456.
Texto completoGad-el-Hak, Ibrahim, Njuki Mureithi, Kostas Karazis y Gary Williams. "Jet cross-flow induced vibrations in rod bundles. Part I: Experimental apparatus and stream-wise vibration results". Nuclear Engineering and Design 401 (enero de 2023): 112046. http://dx.doi.org/10.1016/j.nucengdes.2022.112046.
Texto completoTrebotich, D., G. H. Miller y M. D. Bybee. "A Penalty Method to Model Particle Interactions in DNA-Laden Flows". Journal of Nanoscience and Nanotechnology 8, n.º 7 (1 de julio de 2008): 3749–56. http://dx.doi.org/10.1166/jnn.2008.18340.
Texto completoKashinsky, O. N., N. A. Pribaturin, P. D. Lobanov, A. S. Kurdyumov y V. V. Randin. "Hydrodynamics and heat transfer of a two-phase gas-liquid flow in fuel assemblies". Proceedings of the Mavlyutov Institute of Mechanics 9, n.º 1 (2012): 98–103. http://dx.doi.org/10.21662/uim2012.1.019.
Texto completoLee, Gil Jun, Suk Hwan Chi, Jay Kim y Tae Soo Lee. "Miniature Air Compressor Design Based on Cross-Slider Mechanism". Key Engineering Materials 486 (julio de 2011): 17–20. http://dx.doi.org/10.4028/www.scientific.net/kem.486.17.
Texto completoXiong, Jinbiao, Wenhai Qu, Zenghui Wu y Xu Cheng. "PIV measurement of cross flow in a rod bundle assisted by telecentric optics and matched index of refraction". Annals of Nuclear Energy 120 (octubre de 2018): 540–45. http://dx.doi.org/10.1016/j.anucene.2018.06.024.
Texto completoSaha, S. K. y P. Langille. "Heat Transfer and Pressure Drop Characteristics of Laminar Flow Through a Circular Tube With Longitudinal Strip Inserts Under Uniform Wall Heat Flux". Journal of Heat Transfer 124, n.º 3 (10 de mayo de 2002): 421–32. http://dx.doi.org/10.1115/1.1423907.
Texto completoHutli, Ezddin, Dániel Tar, Valer Gottlasz y Gyorgy Ezsol. "Investigation of Mixing Flow Process Using PIV and PLIF Techniques". Advanced Materials Research 816-817 (septiembre de 2013): 1054–58. http://dx.doi.org/10.4028/www.scientific.net/amr.816-817.1054.
Texto completoXu, Wanhai, Wenqi Qin y Yan Lu. "Application of Control Rods for Passively Suppressing Cross-Flow VIV of an Inclined Flexible Cylinder". Shock and Vibration 2018 (5 de noviembre de 2018): 1–13. http://dx.doi.org/10.1155/2018/8365726.
Texto completoDmitriev, S. M., A. V. Gerasimov, A. A. Dobrov, D. V. Doronkov, A. N. Pronin, A. V. Ryazanov, D. N. Solntsev y A. E. Khrobostov. "Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor". ENERGETIKA. Proceedings of CIS higher education institutions and power engineering associations 63, n.º 2 (27 de marzo de 2020): 151–62. http://dx.doi.org/10.21122/1029-7448-2020-63-2-151-162.
Texto completoShin, Seungwon y S. I. Abdel-Khalik. "Numerical Modeling of Evaporating Thin Liquid Film Instability on a Heated Cylindrical Rod with Parallel and Cross Vapor Flow". Nuclear Science and Engineering 156, n.º 1 (mayo de 2007): 24–39. http://dx.doi.org/10.13182/nse07-a2682.
Texto completoSedaghat, Alireza, Frank S. Castellana, Robert H. Hsu y Robert B. Macduff. "A Noninvasive Technique for the Evaluation of Diversion Cross Flow at the Inlet of a Simulated Fuel Rod Bundle". Nuclear Technology 80, n.º 3 (marzo de 1988): 360–70. http://dx.doi.org/10.13182/nt88-a34060.
Texto completoKapse, A. A., P. R. Dongarwar y R. R. Gawande. "Experimental investigation of turbulent heat transfer performance in internal flow using a star shape cross sectioned twisted rod inserts". Heat and Mass Transfer 53, n.º 1 (26 de abril de 2016): 253–64. http://dx.doi.org/10.1007/s00231-016-1820-7.
Texto completoSun, Hongbiao, Wenqiang Li, Tianda Yu, Yanting Liu y Zhiqiang Zhang. "Research on associated motion simulation method and platform of control rod driving mechanism". Advances in Mechanical Engineering 13, n.º 9 (septiembre de 2021): 168781402110430. http://dx.doi.org/10.1177/16878140211043003.
Texto completoTakeda, Kazuki, Yohann Duguet y Takahiro Tsukahara. "Intermittency and Critical Scaling in Annular Couette Flow". Entropy 22, n.º 9 (4 de septiembre de 2020): 988. http://dx.doi.org/10.3390/e22090988.
Texto completoQu, Wenhai, Zefeng Wang, Jinbiao Xiong y Xu Cheng. "Experimental study of cross flow and lateral pressure drop in a 5 × 5 rod bundle with mixing vane spacer grid". Nuclear Engineering and Design 353 (noviembre de 2019): 110209. http://dx.doi.org/10.1016/j.nucengdes.2019.110209.
Texto completoPlatov, S. I., V. A. Nekit y N. N. Ogarkov. "Determination of Frictional Forces during Wire Rod Drawing Process by Reverse Method". Solid State Phenomena 265 (septiembre de 2017): 1152–56. http://dx.doi.org/10.4028/www.scientific.net/ssp.265.1152.
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