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Journal articles on the topic 'Rod in Cross-Flow'

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Author: Grafiati

Published: 14 March 2023

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1

Tian, W. X., K. Zhang, Y. D. Hou, Y. P. Zhang, S. Z. Qiu, and G. H. Su. "Hydrodynamics of two-phase flow in a rod bundle under cross-flow condition." Annals of Nuclear Energy 91 (May 2016): 206–14. http://dx.doi.org/10.1016/j.anucene.2016.01.025.

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2

IWAMURA, Takamichi, Hiromichi ADACHI, and Makoto SOBAJIMA. "Air-Water Two-Phase Cross Flow Resistance in Rod Bundle." Journal of Nuclear Science and Technology 23, no. 7 (July 1986): 658–60. http://dx.doi.org/10.1080/18811248.1986.9735034.

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3

Upnere, Sabine, Normunds Jekabsons, Sergejs Dementjevs, and 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.

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Experiments on flow-induced vibrations using a closely-packed triangular rod array with a pitch-todiameter ratio of 1.1 in water cross-flow was carried out at Paul Scherrer Institute. The bundle consists of 21 row of five rods in each one. Single flexibly-mounted test rod (TR) is in the fourth row in an otherwise fixed array. The test rod can freely move in the transverse and in-line direction. Two accelerometer sensors were attached at both ends of the TR to measure the rod response on the fluid flow. The effect of flow rate on the stability of the flexibly-mounted TR has been analysed. During experiments, it reveals a set of conditions and tendencies for the flow-induced vibration in the closely-packed multi-rod system.

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4

OSAKABE, Masahiro. "Pressure Loss of Single-Phase Slanting Cross Flow in Rod Bundle." Journal of Nuclear Science and Technology 24, no. 6 (June 1987): 498–500. http://dx.doi.org/10.1080/18811248.1987.9735835.

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5

Zhang, Weizhong, Hiroyuki Yoshida, Yasuo Ose, Akira Ohnuki, Hajime Akimoto, Akitoshi Hotta, and 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.

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6

ZHANG, Weizhong, Hiroyuki YOSHIDA, Yasuo OSE, Akira OHNUKI, and 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.

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7

Osakabe, M., and H. Futamata. "Effect of inserted rod and cross flow on top flooding of pipe." International Journal of Multiphase Flow 22, no. 5 (September 1996): 883–91. http://dx.doi.org/10.1016/0301-9322(96)00032-8.

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8

Pakhomov, A. A., E. A. Khodyakov, V. S. Bocharnikov, V. G. Grin, N. A. Kolobanova, and 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, no. 1 (January 1, 2022): 012006. http://dx.doi.org/10.1088/1755-1315/965/1/012006.

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Abstract The paper presents a theoretical substantiation of the developed design of a rod flow meter for open canals of irrigation systems. The design features of the lattice elements are revealed, the methods of their hydraulic calculation are given. It was found that the lattices were not used as sensitive elements for measuring water flow rates. A feature of the hydraulic calculation of lattice elements is that it is necessary to take into account the following pressure losses: from the degree of restriction of the living section of the flow, from the ratio of the rod width to the size of the gap, from the rod width, from the rod thickness, from the shape of the cross section of the rod. The operability of the proposed flow meter is theoretically substantiated. It is found that with a significant change in the angle α of the lattice deviation, the degree of tension of the elastic element (angle β) increases by 1-3% from the nominal position. An analytical dependence for determining the value of the hydrodynamic pressure is also obtained.

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9

HIGUCHI, Tatsuya, Shinji MATSUNAGA, Michio SADATOMI, and 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.

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10

MORI, Naoki, Syouhei KIYOSAKI, Akimaro KAWAHARA, and 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.

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11

Seo, Ye-Bon, SalaiSargunan S. Paramanantham, Jin-Yeong Bak, Byongjo Yun, and Warn-Gyu Park. "CFD Analysis of Subcooled Flow Boiling in 4 × 4 Rod Bundle." Applied Sciences 10, no. 13 (June 30, 2020): 4559. http://dx.doi.org/10.3390/app10134559.

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Rod bundle flow is an important research field related to reactor cooling in nuclear power plants. Owing to the rapid development of computerized performance assessments, interest in coolant flow analysis using computational fluid dynamics has garnered research interest. Rod bundle flow research data compared with experimental results under various conditions are thus needed. To address this, a boiling model verification study was conducted with reference to experiments. This study adopts the Reynolds-averaged Navier–Stokes equation, a practical analysis method compared to direct numerical simulation and large eddy simulation, including turbulence modeling, to predict the flow of coolant inside a rod bundle. This study also investigates void behavior in low-pressure subcooled flow boiling using a Eulerian approach (two-fluid model). The rod bundle has a length of 0.59 m and a hydraulic diameter of approximately 14.01 mm. At the cross-section at a height of 0.58 m, near the exit, numerical results were compared with the experimental values of the volume fraction of vapor and interfacial area concentration. The simulation results showed good agreement with the experimental data for six different initial conditions with constant density.

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12

Chang, Chao Cheng, and Yao Sheng Hsiao. "Effect of Grain Size on Cross Wedge Rolling of Micro Copper Rod." Key Engineering Materials 622-623 (September 2014): 905–11. http://dx.doi.org/10.4028/www.scientific.net/kem.622-623.905.

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This study investigated the effect of grain size on the cross wedge rolling of micro copper rod. Annealing techniques and equal channel angular extrusion were employed to refine the grains of copper, after which the treated copper was machined to prepare the cylindrical billets with 1 mm diameter for conducting experiments. The billets were rolled between a pair of the dies fixed in a developed cross wedge rolling system to form micro copper rods. The results show that the developed system was able to successfully produced micro copper rods. The grain refinement led to a higher hardness and thus a greater forming load. The rod with fine grans had a larger concave curvature radius of the end face. The grain size clearly influences the material flow in the cross wedge rolling processes of the micro copper rod.

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13

Kenzhegulov, B. Z., S. B. Kenzhegulova, D. B. Alibiyev, and 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, no. 4 (December 30, 2022): 94–105. http://dx.doi.org/10.31489/2022ph4/94-105.

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In this paper, the definition of the temperature distribution field for a rod made of heat-resistant alloy EI48 is introduced. The authors consider for the study a complete rod of circular cross-section of radius R, of limited length L. Studied body is under the influence of a heat flow q from the surface over the entire cross-sectional area of the left end, and heat exchange with the environment occurs on the cross-sectional area of the right end. The rod is thermally insulated along the side surface. The authors consider two cases: the first is the heat flow with intensity q can be set on the area of a small circle with radius r <R, the second is the heat flow can be set on its part, that is, on the area 2 2   R     . During the study, the authors showed that during the thermomechanical process, the strength of each section of the load-bearing structural elements is significantly influenced by the temperature distribution field. The influence of high temperature on the morphology of heat-resistant alloys is also shown. This leads to the fact that in some parts of the structural elements the temperature will be acceptable, and in some — critical. As a result, rapid wear of structural elements and loss of their physical qualities occur. Therefore, mathematical modeling of temperature distribution field for a body of various configurations is an urgent problem. The article presents a method for constructing a mathematical model and a corresponding computational algorithm that allows solving a class of problems to determine the regularities of the temperature distribution field in the elements of rod-shaped structures. To do this, the authors used the energy-variation principle in combination with the finite element method.

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14

Mishchenko, Andrey V. "Stationary temperature field in multi-layered rods with discontinuous of cross section width." Vestnik MGSU, no. 1 (January 2019): 12–21. http://dx.doi.org/10.22227/1997-0935.2019.1.12-21.

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Introduction. Presents a method for modeling a two-dimensional stationary temperature field in a layered rod. The peculiarity of the structure of the rod is the presence of discontinuity of the width of the cross section in the direction of heat flow and multilayer. Identification of the temperature field in such rods is a necessary step in solving the problem of thermoelasticity. The relevance of the problem lies in the development of analytical methods for analysis layered rods of complex geometric shape with thermal effects, with acceptable computational complexity and necessary accuracy. Materials and methods. For a multilayer rod, a method for constructing an approximate solution of the Dirichlet stationary heat conduction problem with a transverse heat flow direction is considered. Within each layer, the temperature distribution function is represented as a sum of two functions. The first function, linear in the direction of the heat flow, reflects the exact solution of the problem for a rectangular layered section. The second function is the correction nonlinear function of two variables. It describes the nonlinear distortions of the temperature field due to the presence of discontinuities in the width of the cross section. The correction function, according to the Fourier method, is represented as a product of a given coordinate function and the sum of the sought amplitudes caused by the width breaks. The functions of the effect of breaking the width on temperature fields in adjacent layers are introduced. An approximate formulation of the Dirichlet problem with integral conjugation conditions on interlayer boundaries is formulated. Results. The parameters of the stationary temperature field were calculated for a seven-layer section of a T-shaped form with alternating layers of carbon and steel. Testing the results of the Ansys program showed good qualitative and quantitative correspondence of two-dimensional temperature fields. Conclusions. The obtained solution satisfactorily describes the temperature field in the cross section of a layered rod in the vicinity of its geometric features. The method is characterized by acceptable laboriousness and accuracy suitable for solving the problem of thermoelasticity of a layered rod.

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15

KUDO, Hiroyuki, Shinji MATSUNAGA, Tatsuya HIGUCHI, Akimaro KAWAHARA, and 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.

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16

Yull Suh, Kune, and Neil E. Todreas. "An Experimental Correlation of Cross-Flow Pressure Drop for Triangular Array Wire-Wrapped Rod Assemblies." Nuclear Technology 76, no. 2 (February 1987): 229–40. http://dx.doi.org/10.13182/nt87-a33877.

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17

Tanaka, Takaaki, Kensuke Usui, Kenji Kouda, and Kazuhiro Nakanishi. "Filtration Behaviors of Rod-Shaped Bacterial Broths in Unsteady-State Phase of Cross-Flow Filtration." JOURNAL OF CHEMICAL ENGINEERING OF JAPAN 29, no. 6 (1996): 973–81. http://dx.doi.org/10.1252/jcej.29.973.

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18

Moorthi, A., and Anil Kumar Sharma. "Investigation of cross flow mixing on rod bundle safety margins using sub-channel analysis framework." Nuclear Engineering and Design 335 (August 2018): 30–43. http://dx.doi.org/10.1016/j.nucengdes.2018.04.026.

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19

Akhmetov, Sayranbek, Anarbay Kudaykulov, and 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.

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A horizontal bar of limited length is considered. The radius of the bar changes linearly along its length. The cross-sectional area of the left end is larger than the right. The lateral surface of the investigated rod is completely insulated. The heat flux is applied to the cross-sectional area of the left end. Heat exchange with the environment takes place through the cross-sectional area of the right end of the rod. The work determines the field of temperature distribution, displacement, three components of deformation and stress, provided that both ends of the rod are rigidly fixed. The amount of bar elongation is also determined when one end of the bar is fixed and the other is free. In case when the two ends of the bar are fixed, the value of the resulting axial compressive force is calculated. In this study the fundamental laws of conservation of energy were used.

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20

Matozinhos, Camila F., Gabriel C. Q. Tomaz, Thien Nguyen, and 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 (February 2021): 108757. http://dx.doi.org/10.1016/j.ijheatfluidflow.2020.108757.

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21

Berdnikov, Vladimir, Konstantin Mitin, and 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, no. 3 (October 1, 2015): 76–88. http://dx.doi.org/10.54362/1818-7919-2015-10-3-76-88.

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The influence of relative cross-section size of an electrically heated U-shaped silicon rod which is placed in a gas-filled rectangle container with isothermal cold walls on conjugate heat transfer in the regime of buoyancy induced convection was numerically studied in three-dimensional formulation. The natural convection equations in the Boussinesq approximation in term temperature, velocity vortex and velocity vector potential were solved by the finite element method. The spatial form of convective flow and temperature fields in liquid and solid body were studied. It was show that spatial form and intensity of convective flows is significantly depends on the cross-section size of U-shaped silicon rod. This is has strong influence on the temperature field in a solid body.

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22

Liu, Bao Jun, Jing Yu Dong, Cheng Ting Liu, Li Ping Guo, Yin Peng Li, and Wu Yi Shan. "Coherent and Co-Current Flow Separator Optimized Experiment." Applied Mechanics and Materials 529 (June 2014): 202–6. http://dx.doi.org/10.4028/www.scientific.net/amm.529.202.

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In order to improve on pump efficiency,rod-pumped well coherent and co-current flow separator is a new type of gas anchor.Through the indoor experiment,researching the influence on gas anchor degassing efficiency by the bottom of coherent and co-current flow pattern was turned into corrugated shape,changing the surface properties and structure of separator, setting up cross walls in the cup ,the relation curve was drawn between the rate of single cups of liquid level drawdown of all kinds of coherent and co-current flow pattern gas-liquid separators at different gas-liquid ratio and degassing efficiency.

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23

KAWAHARA, Akimaro, Tatsuya HIGUCHI, Michio SADATOMI, and 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, no. 1 (2007): 111–22. http://dx.doi.org/10.1299/jpes.1.111.

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24

ZHANG, Weizhong, Hiroyuki YOSHIDA, Yasuo OSE, Akira OHNUKI, Hajime AKIMOTO, Akitoshi HOTTA, and 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.

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25

Qu, Wenhai, Jinbiao Xiong, Shilong Chen, and Xu Cheng. "High-fidelity PIV measurement of cross flow in 5 × 5 rod bundle with mixing vane grids." Nuclear Engineering and Design 344 (April 2019): 131–43. http://dx.doi.org/10.1016/j.nucengdes.2019.01.021.

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26

Pramuditya, Syeilendra, Minoru Takahashi, and Hisashi Ninokata. "Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wire." Annals of Nuclear Energy 87 (January 2016): 803–16. http://dx.doi.org/10.1016/j.anucene.2014.06.053.

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27

Gad-el-Hak, Ibrahim, Njuki Mureithi, Kostas Karazis, and Gary Williams. "Jet cross-flow induced vibrations in rod bundles. Part II: Transverse vibration results and excitation mechanisms." Nuclear Engineering and Design 400 (December 2022): 112044. http://dx.doi.org/10.1016/j.nucengdes.2022.112044.

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28

Zhang, K., Y. D. Hou, W. X. Tian, Y. P. Zhang, G. H. Su, and 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 (September 2018): 192–204. http://dx.doi.org/10.1016/j.expthermflusci.2018.03.009.

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29

Sargeni, A., and 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.

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The paper presents our first results of the exercise III-I-2c from the OECD-NEA UAM-LWR benchmark intended to an elaboration of the methodology of uncertainty propagation. The considered case studied a full PWR core behavior in fast (~0.1 sec) rod ejection transient. According to the benchmark, the core represented a Hot Zero Power state. Authors used brute-force sampling propagating nuclear data and thermo-fluid uncertainties using 3D computational IRSN chain HEMERA. It couples the reactor physics code CRONOS and thermal-hydraulic core code FLICA4. The nuclear data uncertainties were represented in a form of cross sections standard deviations (in percentage of the mean cross sections values) supplied by the UAM team. In addition to the original benchmark, the study includes a case with an increased power peak by supplementary rod ejection, i.e. with higher reactivity. Both the results are similar to what we obtained in the mini-core rod ejection: the power standard deviation follows, in percentage of the mean power, the mean power curve. We split the variance with a direct calculation: once the cross sections are modified and the thermal-hydraulics inputs are kept constant, another time the contrary. The results show that uncertainties dues to nuclear data dominate over ones due to the thermal-flow area. Furthermore, the major contributors in peak-of-power variance lie in a fast group of cross sections.

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30

KAWAHARA, Akimaro, Tatsuya Higuchi, Hiroyuki KUDOU, and 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.

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31

Kennedy, Kevin F. "An Approximate Three-Dimensional Metal Flow Analysis for Shape Rolling." Journal of Engineering for Industry 110, no. 3 (August 1, 1988): 223–31. http://dx.doi.org/10.1115/1.3187873.

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An approximate three-dimensional metal flow analysis for shape rolling is developed. The analysis, which is presently applicable to rod rolling, is based on an upper-bound approach in which an iterative numerical procedure is used to minimize the energy dissipation rate to obtain kinematically admissible velocity field solutions of the rolling problem. Once the velocity field and the final shape of the plastically deforming body are known, then elementary stress analysis techniques are used to determine the force related aspects of the rolling problem. It is assumed that the rolled material is rigid perfectly plastic, and only the purely mechanical aspects of the metal deformation problem in rolling are considered assuming isothermal conditions. The analysis shows good agreement with elongation and roll separating force measurements in the hot rolling of mild carbon steel for a variety of workpiece and roll cross-section geometries commonly used in rod rolling.

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32

MORIMATSU, Yuki, Michio SADATOMI, and 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.

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33

Nader, A. "Magnetic flux diffusion inside a superconducting long rod with square cross section in the flux-flow regime." Physica B: Condensed Matter 321, no. 1-4 (August 2002): 365–67. http://dx.doi.org/10.1016/s0921-4526(02)01076-1.

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34

ZHANG, Weizhong, Hiroyuki YOSHIDA, Yasuo OSE, Akira OHNUKI, Hajime AKIMOTO, Akitoshi HOTTA, and 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, no. 2 (2008): 456–66. http://dx.doi.org/10.1299/jpes.2.456.

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35

Gad-el-Hak, Ibrahim, Njuki Mureithi, Kostas Karazis, and Gary Williams. "Jet cross-flow induced vibrations in rod bundles. Part I: Experimental apparatus and stream-wise vibration results." Nuclear Engineering and Design 401 (January 2023): 112046. http://dx.doi.org/10.1016/j.nucengdes.2022.112046.

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36

Trebotich, D., G. H. Miller, and M. D. Bybee. "A Penalty Method to Model Particle Interactions in DNA-Laden Flows." Journal of Nanoscience and Nanotechnology 8, no. 7 (July 1, 2008): 3749–56. http://dx.doi.org/10.1166/jnn.2008.18340.

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We present a hybrid fluid-particle algorithm to simulate flow and transport of DNA-laden fluids in microdevices. Relevant length scales in microfluidic systems range from characteristic channel sizes of millimeters to micron scale geometric variation (e.g., post arrays) to 10 nanometers for the length of a single rod in a bead-rod polymer representation of a biological material such as DNA. The method is based on a previous fluid-particle algorithm in which long molecules are represented as a chain of connected rods, but in which the physically unrealistic behavior of rod crossing occurred. We have extended this algorithm to include screened Coulombic forces between particles by implementing a Debye-Hückel potential acting between rods. In the method an unsteady incompressible Newtonian fluid is discretized with a second-order finite difference method in the interior of the Cartesian grid domain; an embedded boundary volume-of-fluid formulation is used near boundaries. The bead-rod polymer model is fully coupled to the solvent through body forces representing hydrodynamic drag and stochastic thermal fluctuations. While intra-polymer interactions are modeled by a soft potential, polymer-structure interactions are treated as perfectly elastic collisions. We demonstrate this method on flow and transport of a polymer through a post array microchannel in 2D where the polymer incorporates more realistic physical parameters of DNA, and compare to previous simulations where rods are allowed to cross. We also show that the method is capable of simulating 3D flow in a packed bed micro-column.

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37

Kashinsky, O. N., N. A. Pribaturin, P. D. Lobanov, A. S. Kurdyumov, and 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, no. 1 (2012): 98–103. http://dx.doi.org/10.21662/uim2012.1.019.

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A study was carried out of the hydrodynamics and heat transfer of two-phase flow in the main elements of the heat-exchange circuits of a nuclear power plant: axisymmetric annular channel and an assembly of vertical rods. The features of the distribution of the gas phase in the section of the working sections of the setup were studied. The dependences of the frictional stress and the heat transfer coefficient are obtained for various flow rates of liquid and gas. The interaction of one- and two-phase flows with barriers that overlap a portion of the cross-section of the channels by a spacer grid in the rod assembly and a partition covering 25% of the cross section of the annular channel is considered. The obtained data can be used for verification of modern computational codes.

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38

Lee, Gil Jun, Suk Hwan Chi, Jay Kim, and Tae Soo Lee. "Miniature Air Compressor Design Based on Cross-Slider Mechanism." Key Engineering Materials 486 (July 2011): 17–20. http://dx.doi.org/10.4028/www.scientific.net/kem.486.17.

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Most of the current air compressors are driven by a slider-crank mechanism consisted of the crank, connecting rod, and piston. Complexity of this mechanism, however, restricts miniaturization of air compressors. In this study, a design based on a new mechanism, a hybrid of cross-slider and scotch-yoke mechanism, is adopted to develop an oil-free, light-weighted air compressor for portable medical devices. By eliminating the connecting rod, the mechanism has several advantages in addition to the obvious weight reduction due to the simpler mechanism such as the longer seal life of the seal between the piston and cylinder (so called Teflon cup) and reduced shaking forces. Cylinder pressure time history is obtained based on the ideal gas behavior and the isentropic process. Shaking forces and motor torque are calculated from the dynamics equation of the air compressor. The flow capacity curve of the air compressor is obtained by considering the effect of the clearance volume. An actual prototype was fabricated and tested to demonstrate the feasibility of proposed concepts.

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39

Xiong, Jinbiao, Wenhai Qu, Zenghui Wu, and 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 (October 2018): 540–45. http://dx.doi.org/10.1016/j.anucene.2018.06.024.

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40

Saha, S. K., and 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, no. 3 (May 10, 2002): 421–32. http://dx.doi.org/10.1115/1.1423907.

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Heat transfer and pressure drop characteristics in a circular tube fitted with full-length strip, short-length strip, and regularly spaced strip elements connected by thin circular rods have been investigated experimentally. The strips have been rectangular, square and crossed in cross-section with different aspect ratio. Laminar flow of water and other viscous liquids was considered. The rod diameter and length of the strip-rod assembly and the length of the strips were varied. Isothermal friction factor data has been generated. The heat transfer test section was heated electrically imposing axially and circumferentially constant wall heat flux (UWHF) boundary condition. Reynolds number, Prandtl number, strip length, strip ratio, space ratio, and rod-diameter govern the characteristics. Smaller rod-diameter in the strip-rod assembly or “pinching” of the strips in place rather than connecting the strip elements by rods performs better thermohydraulically. Short-length strips (upto a limited fraction of the test section tube length) perform better than the full-length strip. The friction factor correlation and the correlation for Nusselt number under UWHF condition for full-length strip have been modified to make them suitable for short-length strip as well as regularly-spaced strip elements. Thermal entrance length in the correlations is represented by Graetz number. Friction factor and Nusselt number correlations for short-length strips as well as regularly-spaced strip elements, in the limit, reduce to their full-length counterparts.

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41

Hutli, Ezddin, Dániel Tar, Valer Gottlasz, and Gyorgy Ezsol. "Investigation of Mixing Flow Process Using PIV and PLIF Techniques." Advanced Materials Research 816-817 (September 2013): 1054–58. http://dx.doi.org/10.4028/www.scientific.net/amr.816-817.1054.

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A coolant mixing investigation in a head of a half-size model of VVER-440 fuel assembly (simulator) has been performed at KFKI. The PIV and PLIF measurements have been done under a selected list of power distribution options, flow rates and powers. The experiments were focused on obtaining a data for investigating the trends in temperature difference between the value registered by a thermocouple and that obtained using PLIF technique. The coolant temperature distribution has been measured in many positions along the coolant trajectory and where coolant flow leaves the rod bundle and in the cross section location of thermocouple, thus the dynamics of effect of mixing process is also declared. PIV and LPIF results show their ability to verify the primary results of CFD calculations.

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42

Xu, Wanhai, Wenqi Qin, and Yan Lu. "Application of Control Rods for Passively Suppressing Cross-Flow VIV of an Inclined Flexible Cylinder." Shock and Vibration 2018 (November 5, 2018): 1–13. http://dx.doi.org/10.1155/2018/8365726.

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Laboratory experiments were conducted to investigate the cross-flow (CF) vortex-induced vibration (VIV) suppression effectiveness of an inclined flexible cylinder by using control rods. 4 control rods with a diameter of 0.25D (where D is the diameter of the main cylinder) and outer wall distance between the control rod and the main cylinder of 0.50D were attached to the main cylinder. The uniform flow was simulated by towing the cylinder models along a water tank. The corresponding flow velocity ranged from 0.05 to 1.00 m/s with an interval of 0.05 m/s. Two inclination angle cases (a = 0° and 45°) were selected in the experiment. The inclination angle a referred to the angle between the main cylinder axis and the plane orthogonal to the oncoming flow. The experimental results indicate that the control rods can effectively mitigate the CF VIV responses, such as the bending strain, displacement amplitude, dominant frequency, and dominant mode, of both the vertical (a = 0°) and inclined (a = 45°) flexible cylinders. The suppression effectiveness of the control rods on the 45° inclined cylinder is as good as that on the vertical cylinder, and the average suppressing efficiency of the control rods is even better on the 45° inclined cylinder.

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43

Dmitriev, S. M., A. V. Gerasimov, A. A. Dobrov, D. V. Doronkov, A. N. Pronin, A. V. Ryazanov, D. N. Solntsev, and 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, no. 2 (March 27, 2020): 151–62. http://dx.doi.org/10.21122/1029-7448-2020-63-2-151-162.

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The article presents the results of experimental studies of the local hydrodynamics of the coolant flow in the mixed core of the VVER reactor, consisting of the TVSA-T and TVSA-T mod.2 fuel assemblies. Modeling of the flow of the coolant flow in the fuel rod bundle was carried out on an aerodynamic test stand. The research was carried out on a model of a fragment of a mixed core of a VVER reactor consisting of one TVSA-T segment and two segments of the TVSA-T.mod2. The flow pressure fields were measured with a five-channel pneumometric probe. The flow pressure field was converted to the direction and value of the coolant velocity vector according to the dependencies obtained during calibration. To obtain a detailed data of the flow, a characteristic cross-section area of the model was selected, including the space cross flow between fuel assemblies and four rows of fuel rods of each of the TVSA fuel assemblies. In the framework of this study the analysis of the spatial distribution of the projections of the velocity of the coolant flow was fulfilled that has made it possible to pinpoint regularities that are intrinsic to the coolant flowing around spacing, mixing and combined spacing grates of the TVSA. Also, the values of the transverse flow of the coolant caused by the flow along hydraulically nonidentical grates were determined and their localization in the longitudinal and cross sections of the experimental model was revealed. Besides, the effect of accumulation of hydrodynamic flow disturbances in the longitudinal and cross sections of the model caused by the staggered arrangement of hydraulically non-identical grates was determined. The results of the study of the coolant cross flow between fuel assemblies interaction, i.e. between the adjacent TVSA-T and TVSA-T mod.2 fuel assemblies were adopted for practical use in the JSC of “Afrikantov OKB Mechanical Engineering” for assessing the heat engineering reliability of VVER reactor cores; also, they were included in the database for verification of computational hydrodynamics programs (CFD codes) and for detailed cell-based calculation of the reactor core.

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Shin, Seungwon, and 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, no. 1 (May 2007): 24–39. http://dx.doi.org/10.13182/nse07-a2682.

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45

Sedaghat, Alireza, Frank S. Castellana, Robert H. Hsu, and 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, no. 3 (March 1988): 360–70. http://dx.doi.org/10.13182/nt88-a34060.

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Kapse, A. A., P. R. Dongarwar, and 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, no. 1 (April 26, 2016): 253–64. http://dx.doi.org/10.1007/s00231-016-1820-7.

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Sun, Hongbiao, Wenqiang Li, Tianda Yu, Yanting Liu, and Zhiqiang Zhang. "Research on associated motion simulation method and platform of control rod driving mechanism." Advances in Mechanical Engineering 13, no. 9 (September 2021): 168781402110430. http://dx.doi.org/10.1177/16878140211043003.

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The motion simulation analysis of the control rod drive mechanism is a typical multi-disciplinary cross-coupling problem covering electromagnetic field, flow field, and dynamic field. Ensuring effective simulation accuracy is an important advance for accurately predicting the reliability of nuclear reactors. In this paper, a multi-disciplinary co-simulation method is proposed based on time unit differentiation, which solves the coupling problem of parameters by micro-element thought. It can avoid affecting the accuracy of simulation results due to the inequality of multi-disciplinary parameters in the co-simulation process. This paper takes the nuclear reactor control rod drive mechanism as the verification object. The multi-disciplinary co-simulation platform in Isight is built based on the co-simulation method. By differentiating the overall process of multidisciplinary co-simulation according to time unit and using the same simulation time interval for each discipline, the Newmark method is used to determine the minimum simulation time integration step of each discipline. The multi-field co-simulation is carried out including electromagnetic field, flow field, gravitational field, and motion field of the driving mechanism in the working process. Through comparison with the actual measurement results, the simulation results have an error within 5%, which is better than existing motion simulation results of driving mechanism.

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48

Takeda, Kazuki, Yohann Duguet, and Takahiro Tsukahara. "Intermittency and Critical Scaling in Annular Couette Flow." Entropy 22, no. 9 (September 4, 2020): 988. http://dx.doi.org/10.3390/e22090988.

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The onset of turbulence in subcritical shear flows is one of the most puzzling manifestations of critical phenomena in fluid dynamics. The present study focuses on the Couette flow inside an infinitely long annular geometry where the inner rod moves with constant velocity and entrains fluid, by means of direct numerical simulation. Although for a radius ratio close to unity the system is similar to plane Couette flow, a qualitatively novel regime is identified for small radius ratio, featuring no oblique bands. An analysis of finite-size effects is carried out based on an artificial increase of the perimeter. Statistics of the turbulent fraction and of the laminar gap distributions are shown both with and without such confinement effects. For the wider domains, they display a cross-over from exponential to algebraic scaling. The data suggest that the onset of the original regime is consistent with the dynamics of one-dimensional directed percolation at onset, yet with additional frustration due to azimuthal confinement effects.

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Qu, Wenhai, Zefeng Wang, Jinbiao Xiong, and 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 (November 2019): 110209. http://dx.doi.org/10.1016/j.nucengdes.2019.110209.

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Platov, S. I., V. A. Nekit, and N. N. Ogarkov. "Determination of Frictional Forces during Wire Rod Drawing Process by Reverse Method." Solid State Phenomena 265 (September 2017): 1152–56. http://dx.doi.org/10.4028/www.scientific.net/ssp.265.1152.

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The article pesents the drawing process of the circular cross-section rod. The mechanical model of plastic deformation in the process of wire drawing is represented by the regularities of yielding of metal at the level of forward flow during the rolling based on theoretical solutions proposed by A. I. Tselikov. The method for determination of drawing forces was probed about by decomposing it into two problems of planar deformation and the superposition of these solutions. The results of the theoretical solution of wire drawing task were used to determine the coefficient of friction during the deformation of low carbon steel in diameter 5.5 mm by means of comparison with the known experimental results of the wire drawing efforts. Satisfactory results were obtained for evaluation of frictional forces during deformation under high plastic deformation zone conditions. The obtained values of friction coefficients can be used to solve the wire drawing tasks and under conditions of a high hearth of plastic deformation as well.

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