Статті в журналах з теми "Wire-wrapped rod bundles"
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Ninokata, Hisashi, Apostolos Efthimiadis, and Neil E. Todreas. "Distributed resistance modeling of wire-wrapped rod bundles." Nuclear Engineering and Design 104, no. 1 (October 1987): 93–102. http://dx.doi.org/10.1016/0029-5493(87)90306-2.
Повний текст джерелаSuh, K. Y., N. E. Todreas, and W. M. Rohsenow. "Mixed Convective Low Flow Pressure Drop in Vertical Rod Assemblies: II—Experimental Validation." Journal of Heat Transfer 111, no. 4 (November 1, 1989): 966–73. http://dx.doi.org/10.1115/1.3250812.
Повний текст джерелаDix, Adam, and Seungjin Kim. "A novel friction factor model for wire-wrapped rod bundles." Nuclear Engineering and Design 401 (January 2023): 112104. http://dx.doi.org/10.1016/j.nucengdes.2022.112104.
Повний текст джерелаBovati, Octavio, Mustafa Alper Yildiz, Yassin Hassan, and Rodolfo Vaghetto. "Pressure drop and flow characteristics in partially blocked wire wrapped rod bundles." Annals of Nuclear Energy 165 (January 2022): 108671. http://dx.doi.org/10.1016/j.anucene.2021.108671.
Повний текст джерелаChoi, Sun Rock, Hyungmo Kim, Seok-Kyu Chang, Hae Seob Choi, Dong-Jin Euh, Hyeong-Yeon Lee, and Won Sik Yang. "Assessment of subchannel flow mixing coefficients for wire-wrapped hexagonal fuel rod bundles." Annals of Nuclear Energy 166 (February 2022): 108810. http://dx.doi.org/10.1016/j.anucene.2021.108810.
Повний текст джерелаBovati, Octavio, Mustafa Alper Yildiz, Yassin Hassan, and Rodolfo Vaghetto. "RANS simulations for transition and turbulent flow regimes in wire-wrapped rod bundles." International Journal of Heat and Fluid Flow 90 (August 2021): 108838. http://dx.doi.org/10.1016/j.ijheatfluidflow.2021.108838.
Повний текст джерелаCarajilescov, Pedro, and Elói Fernandez y Fernandez. "Model for subchannel friction factors and flow redistribution in wire-wrapped rod bundles." Journal of the Brazilian Society of Mechanical Sciences 21, no. 4 (December 1999): 589–99. http://dx.doi.org/10.1590/s0100-73861999000400003.
Повний текст джерелаHu, Rui, and Thomas H. Fanning. "A momentum source model for wire-wrapped rod bundles—Concept, validation, and application." Nuclear Engineering and Design 262 (September 2013): 371–89. http://dx.doi.org/10.1016/j.nucengdes.2013.04.026.
Повний текст джерелаKim, Hansol, Yu Min Chen, and Yassin Hassan. "Prediction of pressure drop in hexagonal wire-wrapped rod bundles using artificial neural network." Nuclear Engineering and Design 381 (September 2021): 111365. http://dx.doi.org/10.1016/j.nucengdes.2021.111365.
Повний текст джерелаChen, S. K., Y. M. Chen, and N. E. Todreas. "The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles." Nuclear Engineering and Design 335 (August 2018): 356–73. http://dx.doi.org/10.1016/j.nucengdes.2018.05.010.
Повний текст джерелаSorokin, A., Yu Kuzina, G. Sorokin, and N. Denisova. "MODELING OF HEAT AND MASS TRANSFER PROCESSES IN FUEL ASSEMBLIES OF FAST REACTORS AS PART OF THE CHANNEL-BY-CHANNEL CALCULATION METHOD. GENERALIZED EXCHANGE CHARACTERISTICS FOR SINGLE-PHASE FLOWS OF LIQUID METALS." PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2020, no. 2 (June 26, 2020): 104–30. http://dx.doi.org/10.55176/2414-1038-2020-2-104-130.
Повний текст джерелаCheng, Shih-Kuei, and Neil E. Todreas. "Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters." Nuclear Engineering and Design 92, no. 2 (April 1986): 227–51. http://dx.doi.org/10.1016/0029-5493(86)90249-9.
Повний текст джерелаChen, Y. M., S. K. Chen, and Y. Hassan. "The blockage model of Upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles." Nuclear Engineering and Design 395 (August 2022): 111874. http://dx.doi.org/10.1016/j.nucengdes.2022.111874.
Повний текст джерелаBovati, Octavio, and Yassin Hassan. "Implementation of a CFD methodology for computing subchannel friction factors and split parameters in wire-wrapped rod bundles." Nuclear Engineering and Design 397 (October 2022): 111952. http://dx.doi.org/10.1016/j.nucengdes.2022.111952.
Повний текст джерелаPacio, J., S. K. Chen, Y. M. Chen, and N. E. Todreas. "Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data." Nuclear Engineering and Design 388 (March 2022): 111606. http://dx.doi.org/10.1016/j.nucengdes.2021.111606.
Повний текст джерелаPacio, J., S. K. Chen, Y. M. Chen, and N. E. Todreas. "Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD)." Nuclear Engineering and Design 388 (March 2022): 111607. http://dx.doi.org/10.1016/j.nucengdes.2021.111607.
Повний текст джерелаChen, S. K., Y. M. Chen, and N. E. Todreas. "Corrigendum to “The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles” [Nucl. Eng. Des. 335 (2018) 356–373]." Nuclear Engineering and Design 340 (December 2018): 414. http://dx.doi.org/10.1016/j.nucengdes.2018.10.009.
Повний текст джерелаLyu, Kefeng, Xuelei Sheng, and Xudan Ma. "Thermal-hydraulic Assessment of Seven Wire-wrapped rod Bundle." E3S Web of Conferences 212 (2020): 01009. http://dx.doi.org/10.1051/e3sconf/202021201009.
Повний текст джерелаLYU, Kefeng, Xuelei SHENG, Xudan MA, and Haitao WANG. "CFD Analysis of Scaled Wire-wrapped rod Bundle Cooled by LBE." E3S Web of Conferences 136 (2019): 01044. http://dx.doi.org/10.1051/e3sconf/201913601044.
Повний текст джерелаLi, Yonghua, Meijun Li, and Yangyang Guo. "Analysis of Resistance Characteristics of a 37 Rod Fuel Bundle under Low Reynolds Number." Journal of Energy 2020 (December 2, 2020): 1–8. http://dx.doi.org/10.1155/2020/8861190.
Повний текст джерелаTan, Xuefeng, Bing Wang, Yun Guo, and Miao Hu. "Numerical Investigation of Special Heat Transfer Phenomenon in Wire-Wrapped Fuel Rod of SFR." Micromachines 13, no. 6 (June 11, 2022): 935. http://dx.doi.org/10.3390/mi13060935.
Повний текст джерелаWang, Xi, and Xu Cheng. "Analysis of inter-channel sweeping flow in wire wrapped 19-rod bundle." Nuclear Engineering and Design 333 (July 2018): 115–21. http://dx.doi.org/10.1016/j.nucengdes.2018.04.008.
Повний текст джерелаHou, Junren, Qingkang Song, Haojie Leng, Chaohui Xue, Yuan Yuan, and Yuan Zhou. "A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior." Progress in Nuclear Energy 154 (December 2022): 104469. http://dx.doi.org/10.1016/j.pnucene.2022.104469.
Повний текст джерелаTodreas, Neil, Shih-Kuei Chen, and Julio Pacio. "Adventures in study of the pressure losses in wire-wrapped rod bundle arrays." Nuclear Engineering and Design 370 (December 2020): 110910. http://dx.doi.org/10.1016/j.nucengdes.2020.110910.
Повний текст джерелаWang, Han, Qincheng Bi, and Laurence K. H. Leung. "Heat transfer from a 2 × 2 wire-wrapped rod bundle to supercritical pressure water." International Journal of Heat and Mass Transfer 97 (June 2016): 486–501. http://dx.doi.org/10.1016/j.ijheatmasstransfer.2016.02.036.
Повний текст джерелаChilds, Mason, Rodolfo Vaghetto, Philip Jones, Nolan Goth, and Yassin Hassan. "Experimental determination and analysis of the transverse pressure difference in a wire-wrapped rod bundle." International Journal of Heat and Mass Transfer 170 (May 2021): 120958. http://dx.doi.org/10.1016/j.ijheatmasstransfer.2021.120958.
Повний текст джерелаChai, Xiang, Xiaojing Liu, Jinbiao Xiong, and Xu Cheng. "Numerical investigation of thermal-hydraulic behaviors in a LBE-cooled 19-pin wire-wrapped rod bundle." Progress in Nuclear Energy 119 (January 2020): 103044. http://dx.doi.org/10.1016/j.pnucene.2019.103044.
Повний текст джерелаChai, Xiang, Xiaojing Liu, Jinbiao Xiong, and Xu Cheng. "CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle." Nuclear Engineering and Design 344 (April 2019): 107–21. http://dx.doi.org/10.1016/j.nucengdes.2019.01.019.
Повний текст джерелаCesna, ? ? "Experimental Study of Heat Transfer from a Rod Bundle of Wire-Wrapped Tubes in Axial Air Flow." Heat Transfer Research 35, no. 7-8 (2004): 549–62. http://dx.doi.org/10.1615/heattransres.v35.i78.80.
Повний текст джерелаSu, Xing-Kang, Xian-Wen Li, Lu Zhang, Long Gu, and Da-Jun Fan. "Thermal-hydraulic study in a wire-wrapped 19-rod bundle based on an isotropic four-equation model." Annals of Nuclear Energy 178 (December 2022): 109343. http://dx.doi.org/10.1016/j.anucene.2022.109343.
Повний текст джерелаWang, Shunqi, Han Wang, Jinguang Zang, Junfeng Wang, and Yanping Huang. "Numerical simulation of the thermal-hydraulic characteristics of supercritical carbon dioxide in a wire-wrapped rod bundle." Applied Thermal Engineering 198 (November 2021): 117443. http://dx.doi.org/10.1016/j.applthermaleng.2021.117443.
Повний текст джерелаFernandez y Fernandez, Elói, and Pedro Carajilescov. "Static pressure and wall shear stress distributions in air flow in a seven wire-wrapped rod bundle." Journal of the Brazilian Society of Mechanical Sciences 22, no. 2 (2000): 291–302. http://dx.doi.org/10.1590/s0100-73862000000200012.
Повний текст джерелаKiss, Attila, and Bence Mervay. "Numerical analysis on the thermal hydraulic effect of wrapped wire spacer in a four rod fuel bundle." Nuclear Engineering and Design 342 (February 2019): 276–307. http://dx.doi.org/10.1016/j.nucengdes.2018.11.024.
Повний текст джерелаZhong, Yunke, Lian Hu, Deqi Chen, Haidong Liu, Dewen Yuan, and Wenxing Liu. "CFD simulation on the flow and heat transfer characteristics of mist flow in wire-wrapped rod bundle." Nuclear Engineering and Design 345 (April 2019): 62–73. http://dx.doi.org/10.1016/j.nucengdes.2019.02.003.
Повний текст джерелаBovati, Octavio, and Yassin Hassan. "Analysis of the turbulent flow in a partially blocked wire-wrapped rod bundle using LES with wall functions." International Journal of Heat and Fluid Flow 97 (October 2022): 109041. http://dx.doi.org/10.1016/j.ijheatfluidflow.2022.109041.
Повний текст джерелаLiang, Yu, Dalin Zhang, Yutong Chen, Kui Zhang, Wenxi Tian, Suizheng Qiu, and Guanghui Su. "An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle." Applied Thermal Engineering 174 (June 2020): 115283. http://dx.doi.org/10.1016/j.applthermaleng.2020.115283.
Повний текст джерелаHu, Z. X., H. B. Li, J. Q. Tao, D. Liu, and H. Y. Gu. "Experimental study on heat transfer of supercritical water flowing upward and downward in 2 × 2 rod bundle with wrapped wire." Annals of Nuclear Energy 111 (January 2018): 50–58. http://dx.doi.org/10.1016/j.anucene.2017.08.042.
Повний текст джерелаChang, Seok-Kyu, Dong-Jin Euh, Hae Seob Choi, Hyungmo Kim, Sun Rock Choi, and Hyeong-Yeon Lee. "Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor." Nuclear Engineering and Technology 48, no. 2 (April 2016): 376–85. http://dx.doi.org/10.1016/j.net.2015.12.013.
Повний текст джерелаPodila, Krishna, and Yanfei Rao. "Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water." Journal of Nuclear Engineering and Radiation Science 4, no. 1 (December 4, 2017). http://dx.doi.org/10.1115/1.4037747.
Повний текст джерелаMenezes, Craig, Rodolfo Vaghetto, and Yassin A. Hassan. "Experimental Investigation of the Subchannel Axial Pressure Drop and Hydraulic Characteristics of a 61-Pin Wire Wrapped Rod Bundle." Journal of Fluids Engineering 144, no. 5 (January 12, 2022). http://dx.doi.org/10.1115/1.4052745.
Повний текст джерелаChilds, Mason, Robert Muyshondt, Rodolfo Vaghetto, Duy Thien Nguyen, and Yassin Hassan. "Experimental Study on the Effect of Localized Blockages on the Friction Factor of a 61-Pin Wire-Wrapped Bundle." Journal of Fluids Engineering 142, no. 11 (September 4, 2020). http://dx.doi.org/10.1115/1.4048140.
Повний текст джерелаKim, Hansol, Joseph Seo, and Yassin Hassan. "Prediction of flow regime boundary and pressure drop for hexagonal wire-wrapped rod bundles using artificial neural networks." Physics of Fluids, September 8, 2022. http://dx.doi.org/10.1063/5.0110385.
Повний текст джерелаPacio, J., S. K. Chen, Y. M. Chen, and N. E. Todreas. "Corrigendum to “Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: the Pacio-Chen-Todreas Detailed model (PCTD)” [Nucl. Eng. Des. 388 (2022) 111607]." Nuclear Engineering and Design, June 2022, 111846. http://dx.doi.org/10.1016/j.nucengdes.2022.111846.
Повний текст джерелаWang, Han, Muchuan Sun, Dajun Fan, Hao Hu, Peiqi Liang, and Jianguo Yan. "Experimental Investigation of the Crossflow of Water in a 7-Pin Wire-Wrapped Rod Bundle." SSRN Electronic Journal, 2022. http://dx.doi.org/10.2139/ssrn.4086699.
Повний текст джерелаMenezes, Craig, Trevor Melsheimer, Dalton W. Pyle, Matthew Kinsky, and Yassin Hassan. "Flow Characteristics within an Interior Subchannel of a 61-pin Wire-Wrapped Hexagonal Rod Bundle with a Porous Blockage." Physics of Fluids, January 15, 2023. http://dx.doi.org/10.1063/5.0138487.
Повний текст джерелаDong, Kejian, Shakeel Ahmad, Shahid Ali Khan, Peng Ding, Wenhuai Li, and Jiyun Zhao. "Thermal‐hydraulic analysis of wire‐wrapped rod bundle in lead‐based fast reactor with non‐uniform heat flux." International Journal of Energy Research, June 28, 2022. http://dx.doi.org/10.1002/er.8316.
Повний текст джерелаQuan, Zhengting, Adam Dix, Ran Kong, Seungjin Kim, Mamoru Ishii, and Mitchell T. Farmer. "Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium Cartridge Loop in Versatile Test Reactor." Nuclear Science and Engineering, July 5, 2022, 1–17. http://dx.doi.org/10.1080/00295639.2022.2082232.
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