Academic literature on the topic 'Wire-wrapped rod bundles'
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Journal articles on the topic "Wire-wrapped rod bundles"
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.
Full textSuh, 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.
Full textDix, 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.
Full textBovati, 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.
Full textChoi, 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.
Full textBovati, 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.
Full textCarajilescov, 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.
Full textHu, 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.
Full textKim, 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.
Full textChen, 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.
Full textDissertations / Theses on the topic "Wire-wrapped rod bundles"
Kindfuller, Vincent John. "Improvements to the Cheng-Todreas wire-wrapped rod bundle friction factor correlation in response to pin number and in the transition flow region." Thesis, Massachusetts Institute of Technology, 2016. http://hdl.handle.net/1721.1/106697.
Full textThis 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 51-52).
The Cheng-Todreas Detailed (CTD) Pressure Drop Correlation (1986) is the most accurate correlation for measuring the pressure drop of sodium coolant through a Sodium-Cooled Fast Reactor (SFR). Although CTD is the most accurate correlation, there is room for improvement with new data and modern ways to visualize data and check the accuracy of changes easily. This thesis attempts to offer a method for altering the CTD correlation to better account for changing pin numbers in SFR assemblies, and a better fit for the correlation to the data in the transition flow region between turbulent and laminar flow. Although CTD is more accurate than other correlations, it shows an inverse response to changing pin number in some geometries of bundle assemblies. In this thesis, a method is laid out to attempt to correct for that inverse response. Although no successful conclusion was reached, the thesis also offers a method for future attempts at improvement. In addition, a set of Matlab codes are offered that allow changes to be easily attempted and checked for validity. In addition, examining the data points of bundles in the transition flow regime shows possibilities for improving the accuracy of the correlation in that flow region. Two changes are implemented in this thesis: a change to the equation for the boundary between laminar and transition flow, and a change to the transition region friction factor equation. Both changes, when implemented, offer slight improvements to the overall accuracy and precision of the Cheng-Todreas Pressure Drop Correlation..
by Vincent John Kindfuller.
S.B.
Conference papers on the topic "Wire-wrapped rod bundles"
Brockmeyer, Landon, Lane Carasik, Elia Merzari, and Yassin Hassan. "CFD Investigation of Wire-Wrapped Fuel Rod Bundle Inner Subchannel Behavior and Dependency on Bundle Size." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60831.
Full textHeidet, F., and S. Yoon. "Evaluation of Pressure Drop Correlations for the Wire-wrapped Rod Bundles." In Transactions - 2020 Virtual Conference. AMNS, 2020. http://dx.doi.org/10.13182/t122-31608.
Full textHeidet, F., and S. Yoon. "Evaluation of Pressure Drop Correlations for the Wire-wrapped Rod Bundles." In Transactions - 2020 Virtual Conference. AMNS, 2020. http://dx.doi.org/10.13182/t31608.
Full textWu, Jie, and Jiejin Cai. "Initial Wire-Wrapped Angle Optimization Analysis of a Liquid Lead-Bismuth Cooled Fuel Assembly Based on OpenFOAM." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-92097.
Full textSmith, Jeffrey G., Bruce R. Babin, W. David Pointer, and Paul F. Fischer. "Effects of Mesh Density and Flow Conditioning in Simulating 7-Pin Wire Wrapped Fuel Pins." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48306.
Full textPucciarelli, Andrea. "Results of a LES Application to LBE Turbulent Flow in a Wire-Wrapped Single Rod Channel." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-64153.
Full textGuo, Jinsong, Xueyuan Zhang, Haiqi Zhao, Daogang Lu, and Yuhao Zhang. "Three-Dimensional Numerical Simulation of the Natural Circulation Characteristics Based on PLANDTL-DHX for Different Modeling Methods of the Core." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-92364.
Full textJeong, Jae-Ho. "Assessment of RANS Based CFD Methodology Using JAEA Fuel Assembly Experiment." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-61038.
Full textLi, Minggang, Jun Wang, Changhua Nie, Xiao Yan, Yanping Huang, Zumao Yang, and Feng Xie. "Numerical Investigation of Flow and Heat Transfer Characteristics in Wire-Wrap Tight Lattice 19-Rod Bundle." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15832.
Full textMcCreery, Glenn E., Hugh M. McIlroy, Kurt D. Hamman, and Hongbin Zhang. "Design of Wire-Wrapped Rod Bundle Matched Index-of-Refraction Experiments." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48585.
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