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Journal articles on the topic 'Spacer Grids'

Author: Grafiati

Published: 4 June 2021

Last updated: 26 July 2025

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1

Yang, Sun Kyu, and Moon Ki Chung. "Turbulent Flow Through Spacer Grids in Rod Bundles." Journal of Fluids Engineering 120, no. 4 (1998): 786–91. http://dx.doi.org/10.1115/1.2820739.

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The effects of the spacer grids with mixing vanes in rod bundles on the turbulent structure were investigated experimentally. The detailed hydraulic characteristics in subchannels of a 5 × 5 rod bundle with mixing spacer grids were measured upstream and downstream of the spacer grid by using a one component LDV (Laser Doppler Velocimetry). Axial velocity and turbulent intensity, skewness factor, and flatness factor were measured. The turbulence decay behind spacer grids was obtained from measured data. The trend of turbulence decay behaves in a similar way as turbulent flow through mesh grids

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2

Kim, Minhee, and Ihn Namgung. "Refinement of Finite Element Method Analysis Model of Pressurized Water Reactor Nuclear Fuel Spacer Grid Based on Experimental Data." Energies 18, no. 3 (2025): 528. https://doi.org/10.3390/en18030528.

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A Finite Element Method (FEM) analysis of the nuclear fuel spacer grid was conducted to assess the strength of components for the safety of nuclear power plants. The fuel assembly consists of fuel rods, upper end-fitting, lower end-fitting, guide tubes, and spacer grids. Spacer grids play a critical role in maintaining the proper spacing between fuel rods within a fuel assembly and ensuring smooth coolant flow. This role becomes particularly crucial during unforeseen emergencies, such as seismic loads, where minimizing deformation caused by external forces is essential. Therefore, this study p

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3

Beloborodov, Alexey V., Yuri V. Chuguy, Leonid V. Finogenov, Anna A. Gushchina, Yuri A. Lemeshko, and Peter S. Zav’yalov. "3D Inspection of Fuel Assembly Components." Key Engineering Materials 437 (May 2010): 155–59. http://dx.doi.org/10.4028/www.scientific.net/kem.437.155.

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Safety increasing of nuclear reactors is urgent problem for atomic industry. It takes 100% noncontact dimensional inspection of nuclear reactor components. Optoelectronic methods and systems for 3D inspection of fuel assembly elements, including spacer grids and fuel elements, are presented. The universal structured light method for 3D inspection of Russian and western grid spacers using diffraction elements is developed. For fuel elements inspection one considers the shadow method which allows one to implement full inspection of articles under transported along the automatic production line.

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4

Wang, Feng, Yanxin Liu, Zanlin Yu, et al. "General and robust covalently linked graphene oxide affinity grids for high-resolution cryo-EM." Proceedings of the National Academy of Sciences 117, no. 39 (2020): 24269–73. http://dx.doi.org/10.1073/pnas.2009707117.

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Affinity grids have great potential to facilitate rapid preparation of even quite impure samples in single-particle cryo-electron microscopy (EM). Yet despite the promising advances of affinity grids over the past decades, no single strategy has demonstrated general utility. Here we chemically functionalize cryo-EM grids coated with mostly one or two layers of graphene oxide to facilitate affinity capture. The protein of interest is tagged using a system that rapidly forms a highly specific covalent bond to its cognate catcher linked to the grid via a polyethylene glycol (PEG) spacer. Importan

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5

Peña-Monferrer, C., J. L. Muñoz-Cobo, and S. Chiva. "CFD Turbulence Study of PWR Spacer-Grids in a Rod Bundle." Science and Technology of Nuclear Installations 2014 (2014): 1–15. http://dx.doi.org/10.1155/2014/635651.

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Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow dynamics and heat transfer phenomena along the fuel rods. This work presents the analysis of the turbulence effects of a split-type and swirl-type spacer-grid geometries on single phase in a PWR (pressurized water reactor) rod bundle. Various computational fluid dynamics (CFD) calculations have been performed and the results validated with the experiments of the OECD/NEA-KAERI rod bundle CFD blind benchmark exercise on turbulent mixing in a rod bundle with spacers at the MATiS-H facility. Simula

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6

Kim, Minhee, and Ihn Namgung. "An Investigation of the Stiffness Characteristics of a PWR Nuclear Fuel Spacer Grid by a 3D Shell Model." Energies 17, no. 23 (2024): 6066. https://doi.org/10.3390/en17236066.

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The structural integrity of fuel assemblies hinges significantly on the effectiveness of spacer grids. In this paper, we introduce a novel approach to assess the structural robustness of the mid-spacer grid (SG) of the PLUS7 fuel assembly (FA) using 3D shell elements. Any excessive external load from seismic activity can be broken down into two perpendicular components, namely normal load and shear load. The decomposition enables easy assessment of the structural integrity of the fuel spacer grid for any external loads. From the analysis, the reaction force of normal input displacement is arou

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7

Kolev, Nikolay Ivanov. "ICONE15-10031 HOW SPACER GRIDS INFLUENCE MULTIPHASE FLOW PROCESSES?" Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_12.

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8

Hochreiter, L. E., M. J. Loftus, F. J. Erbacher, P. Ihle, and K. Rust. "POST CHF EFFECTS OF SPACER GRIDS AND." Multiphase Science and Technology 7, no. 1-4 (1993): 185–269. http://dx.doi.org/10.1615/multscientechn.v7.i1-4.40.

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9

Jeon, Sang Youn, and Young Shin Lee. "An Estimation of the Dynamic Buckling Load for the Spacer Grid of Pressurized Water Reactor Fuel Assembly." Key Engineering Materials 326-328 (December 2006): 1603–6. http://dx.doi.org/10.4028/www.scientific.net/kem.326-328.1603.

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This study contains an estimation of the dynamic buckling load for the spacer grid of fuel assembly in pressurized water reactor. Three different estimation methods were proposed for the calculation of the dynamic buckling loads of spacer grid. The dynamic impact tests and analyses were performed to evaluate the impact characteristics of the spacer grids and to predict the dynamic buckling load of the full size spacer grid. The estimation results were compared with the test results for the verification of the estimation methods.

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10

Lo, Simon, and Joseph Osman. "CFD Modeling of Boiling Flow in PSBT 5×5 Bundle." Science and Technology of Nuclear Installations 2012 (2012): 1–8. http://dx.doi.org/10.1155/2012/795935.

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Three-dimensional computational fluid dynamics (CFD) method was used to model the boiling two-phase flow in one of the PSBT 5-by-5 rod bundle tests. The rod bundle with all the spacers was modeled explicitly using unstructured computational grids. The six-equation, two-fluid model with the wall boiling model was used to model the boiling two-phase flows in the bundle. The computed void fractions compare well with the measured data at the measuring plane. In addition to the averaged void data, the CFD results give a very detailed picture of the flow and void distributions in the bundle and how

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11

Ječmenica, Radomir, Davor Grgić, and Mario Matijević. "Influence of Spacer Grids Homogenization on Core Reactivity and Axial Power Distribution." Journal of Energy - Energija 68, no. 2-3 (2022): 199–208. http://dx.doi.org/10.37798/2019682-3203.

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The paper presents the influence of spacer grid homogenization during cross section generation on core reactivity and axial power distribution. Homogenization calculation was performed at fuel assembly level using FA2D code. The first approach is to smear uniformly all centrally located spacer grids along 120 inches of fuel assembly and carry out 2D transport calculation. The second approach is to smear spacer grid within 6 inches of fuel assembly and perform homogenization calculation. That composition is then assigned to closest 6 in axial subdivision of the core calculation. The last analys

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12

Jeon, Sang Youn, Kyu Tae Kim, and Young Shin Lee. "A Study on the Static Buckling Load Estimation of the Spacer Grid in the Pressurized Water Reactor Fuel Assembly." Key Engineering Materials 353-358 (September 2007): 2581–84. http://dx.doi.org/10.4028/www.scientific.net/kem.353-358.2581.

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This study contains several estimation methods of the static buckling load for the spacer grid of nuclear fuel assembly in pressurized water reactor. Three different estimation methods were proposed for the calculation of the static buckling loads of spacer grid. The linear and non-linear static buckling analyses were performed to estimate the static buckling load of the spacer grids using ANSYS program. The analyses results were compared with the static buckling test results. Based on the analysis and test results, the applicability of the proposed estimation method for the static buckling lo

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13

Cesna, B., and M. Valincius. "Local heat transfer coefficient near the spacer grids." Kerntechnik 76, no. 4 (2011): 249–53. http://dx.doi.org/10.3139/124.110157.

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14

Proma, Monisha Podder, Humayra Adiba, Akifa Mustafiza, and Abdus Sattar Mollah. "Effects of Spacer Grid on Thermal-Hydraulic Performance of Fluid in a 4×4 Fuel Channel of VVER-1200 by using Ansys Fluent." WSEAS TRANSACTIONS ON APPLIED AND THEORETICAL MECHANICS 19 (December 31, 2024): 170–83. https://doi.org/10.37394/232011.2024.19.19.

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In this paper, the structural design of a spacer grid of VVER-1200 has been done by Fusion 360 software. Simulation has been done using Ansys fluent software of temperature profile, velocity profile, and pressure drop along the flow path of fuel assembly to find out the optimum spacing between two spacer grids in a reactor core. Proper spacing between spacer grids helps maintain an optimal coolant, temperature, velocity, and pressure drop ensuring efficient heat removal. This, in turn, contributes to the overall efficiency of the nuclear reactor and generates green energy. The convective heat

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15

Lee, Young Ho, and Hyung Kyu Kim. "Preliminary Study on the Fretting Wear Reliability of an Annular Nuclear Fuel." Materials Science Forum 706-709 (January 2012): 2535–39. http://dx.doi.org/10.4028/www.scientific.net/msf.706-709.2535.

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Recently, a dual-cooled fuel (i.e. annular fuel) which is compatible with current operating PWR plants has been proposed in order to increase both power densities and safety margins. Due to the design concept that is compatible with current PWR plants, however, when compared with a current solid nuclear fuel it shows a narrow gap between fuel rods and needs to modify spacer grid shapes and their positions. Because a flow-induced vibration by fast primary coolant is inevitable phenomenon, it is necessary to examine the fretting wear behavior between an annular fuel and designed spacer grids. In

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16

Tian, Zihao, Lixin Yang, Shuang Han, et al. "Numerical Investigation on the Flow Characteristics in a 17 × 17 Full-Scale Fuel Assembly." Energies 13, no. 2 (2020): 397. http://dx.doi.org/10.3390/en13020397.

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In a previous study, several computational fluid dynamics (CFD) simulations of fuel assembly thermal-hydraulic problems were presented that contained fewer fuel rods, such as 3 × 3 and 5 × 5, due to limited computer capacity. However, a typical AFA-3G fuel assembly consists of 17 × 17 rods. The pressure drop levels and flow details in the whole fuel assembly, and even in the pressurized water reactor (PWR), are not available. Hence, an appropriate CFD method for a full-scale 17 × 17 fuel assembly was the focus of this study. The spacer grids with mixing vanes, springs, and dimples were conside

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17

Dyk, Štěpán, and Vladimír Zeman. "Bifurcations in Mathematical Model of Nonlinear Vibration of the Nuclear Fuel Rod." Applied Mechanics and Materials 821 (January 2016): 207–12. http://dx.doi.org/10.4028/www.scientific.net/amm.821.207.

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The paper deals with nonlinear phenomena that occurs during vibration of nuclear fuel rod (FR). The FR is considered as a system consisting of two impact-interacting subsystems FR cladding (zircalloy tube) and fuel pellets stack placed inside FR cladding. Between both subsystems, there is a small radial clearance. The FR is bottom-end-fixed, and at eight equidistant levels, the FR cladding is supported by spacer grids (SG). Both subsystems are modelled by means of finite element method for one-dimensional Euler-Bernoulli continua. During fuel assembly (FA) motion caused by pressure pulsations

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18

Dominguez-Ontiveros, Elvis E., Yassin A. Hassan, Michael E. Conner, and Zeses Karoutas. "Experimental benchmark data for PWR rod bundle with spacer-grids." Nuclear Engineering and Design 253 (December 2012): 396–405. http://dx.doi.org/10.1016/j.nucengdes.2012.09.003.

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19

Jayanti, S., and K. Rajesh Reddy. "Effect of spacer grids on CHF in nuclear rod bundles." Nuclear Engineering and Design 261 (August 2013): 66–75. http://dx.doi.org/10.1016/j.nucengdes.2013.03.044.

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20

Song, Kee-nam, Kyung-ho Yoon, Jae-yong KIm, Tae-hyun Chun, and Kang-hee Lee. "ICONE15-10125 PERFORMANCE ANALYSES AND TESTS ON THE KAERI DEVISED SPACER GRIDS FOR PWRS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_51.

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21

Juklíček, Jakub, and Václav Železný. "CFD ANALYSIS OF THE SPACER GRIDS AND MIXING VANES EFFECT ON THE FLOW IN THE CHOSEN PART OF THE TVSA-T FUEL ASSEMBLY." Acta Polytechnica 55, no. 5 (2015): 324. http://dx.doi.org/10.14311/ap.2015.55.0324.

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<p>CFD is a promising and widely spread tool for a flow simulation in nuclear reactor fuel assemblies. One of the limiting factors is the complicated geometry of a spacer grid. It leads to the computational mesh with high number of cells and with possibility of decreasing quality. Therefore an approach to simulate the flow as precisely as possible and simultaneously in a reasonable computational expense has to be chosen. The goal of the following CFD analysis is to obtain the detailed velocity field in a precise geometry of <br /> a chosen part of the TVSA-T fuel assembly. This kin

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22

Turankok, N., T. Lohez, V. Biscay, and L. Rossi. "Velocity and pressure fluctuations downstream analytical spacer grids: Structure and transport." Nuclear Engineering and Design 430 (December 2024): 113682. http://dx.doi.org/10.1016/j.nucengdes.2024.113682.

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23

Ferrari, Giovanni, Giulio Franchini, Prabakaran Balasubramanian, et al. "Nonlinear vibrations of a nuclear fuel rod supported by spacer grids." Nuclear Engineering and Design 361 (May 2020): 110503. http://dx.doi.org/10.1016/j.nucengdes.2019.110503.

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24

Schettino, C. F. M., J. P. Gouvêa, and N. Medeiros. "Analyses of spacer grids compression strength and fuel assemblies structural behavior." Nuclear Engineering and Design 260 (July 2013): 93–103. http://dx.doi.org/10.1016/j.nucengdes.2013.03.008.

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25

Lys, Stepan. "Analysis of Computer Modelling Results on Fuel Rods Strength and Condition at Reduced or Absent Cooling Caused by Accident." Energy Engineering and Control Systems 7, no. 1 (2021): 7–16. http://dx.doi.org/10.23939/jeecs2021.01.007.

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The paper describes the phenomenology of fuel rod behaviour in severe accident. As an example, an experiment is described resulting in severe damage of 19 fuel rod assembly of VVER type; it was carried out in the CORA facility in 1993 (Research Centre, Karlsruhe, Germany). Testing conditions and results of post-test investigations of fuel assembly are given. The fuel rod code RAPTA-SFD is briefly dealt with; the code was a participant in the International Standard Problem ISP-36. The basic results are presented acquired by computer modelling CORA-W2 experiment using RAPTA-SFD code. Among the p

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26

Zavyalov, Petr S., Dmitry R. Khakimov, Anna A. Guschina, Alexey V. Beloborodov, and Evgeny V. Vlasov. "APPLICATION OF DIFFRACTIVE OPTICAL ELEMENTS FOR OPTICAL-ELECTRONIC DIMENSIONAL INSPECTION SYSTEMS." Interexpo GEO-Siberia 8 (May 21, 2021): 3–16. http://dx.doi.org/10.33764/2618-981x-2021-8-3-16.

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The work is devoted to the application of diffractive optical elements in systems using the structured illumination method to the geometric parameters inspection of industrial articles. The objects of inspection in these systems are: weapon barrels, fuel pellets, fuel elements, spacer grids, ceramic ring insulators. The used diffractive optical elements are computer-synthesized holograms that focus laser radiation into geometric shapes, the configuration of which is optimally combined with the inspected objects shape.

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27

Rezende, Renato Paulo, and Mauricio David Martins das Neves. "Microstructural Characterization of Joints of Inconel 718 Brazed on Vacuum Furnace." Materials Science Forum 1012 (October 2020): 354–59. http://dx.doi.org/10.4028/www.scientific.net/msf.1012.354.

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The spacer grids are part of the Fuel Element (FE) set of the PWR (Pressurized Water Reactor) type reactor. These grids maintain the position of the fuel rods within the arrangement of the FE, conserving among them the spacing necessary for the operation of the reactor. The grids are manufactured from the union of the intersecting points of stamped strips of Base Material (BM) Inconel 718, by a joint process called brazing. The addition metal (AM) used consists of a brazing paste based on Ni-Cr-P (nickel-chromium-phosphorus), which is added dropwise in the intersection of grids with a clearanc

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28

Choi, M. H., H. S. Kang, K. H. Yoon, and K. N. Song. "Vibration analysis of a dummy fuel rod continuously supported by spacer grids." Nuclear Engineering and Design 232, no. 2 (2004): 185–96. http://dx.doi.org/10.1016/j.nucengdes.2003.11.007.

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29

Caraghiaur, Diana, Henryk Anglart, and Wiktor Frid. "Experimental investigation of turbulent flow through spacer grids in fuel rod bundles." Nuclear Engineering and Design 239, no. 10 (2009): 2013–21. http://dx.doi.org/10.1016/j.nucengdes.2009.05.029.

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30

Saini, Nadish, and Igor A. Bolotnov. "Interface capturing simulations of droplet interaction with spacer grids under DFFB conditions." Nuclear Engineering and Design 364 (August 2020): 110685. http://dx.doi.org/10.1016/j.nucengdes.2020.110685.

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31

Choi, Tong Soo, and Hee Cheon NO. "An improved RELAP5/MOD3.3 reflood model considering the effect of spacer grids." Nuclear Engineering and Design 250 (September 2012): 613–25. http://dx.doi.org/10.1016/j.nucengdes.2012.06.025.

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32

SONG, Kee-nam, and Soo-bum LEE. "Performance Analysis and Test on the KAERI Devised Spacer Grids for PWRs." Journal of Power and Energy Systems 2, no. 1 (2008): 47–56. http://dx.doi.org/10.1299/jpes.2.47.

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33

Ren, Quan-yao, Wen-xiong Zhou, Si-jia Du, Zhong-chun Li, and Liang-ming Pan. "Sub-channel flow regime maps in vertical rod bundles with spacer grids." International Journal of Heat and Mass Transfer 122 (July 2018): 1138–52. http://dx.doi.org/10.1016/j.ijheatmasstransfer.2018.01.133.

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34

Wei, Zonglan, Yu Zhang, and Songtao Liu. "ICONE23-1150 LARGE EDDY SIMULATION OF TURBULENT FLOW IN THE ROD BUNDLE WITH DIFFERENT SPACER GRIDS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–1—_ICONE23–1. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-1_82.

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35

Krapivtsev, Veniamin Grigor’evich, Pavel Vladimirovich Markov, and Vladimir Ivanovich Solonin. "Fluid flow and heat transfer in fuel rods assembly with modified spacer grids." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2015, no. 3 (2015): 97–105. http://dx.doi.org/10.26583/npe.2015.3.10.

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36

IKEDA, Kazuo, and Masaya HOSHI. "Flow Characteristics in Spacer Grids Measured by Rod-embedded Fiber Laser Doppler Velocimetry." Journal of Nuclear Science and Technology 44, no. 2 (2007): 194–200. http://dx.doi.org/10.1080/18811248.2007.9711273.

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37

In, Wang Kee, Dong Seok Oh, and Tae Hyun Chun. "Empirical and Computational Pressure Drop Correlations for Pressurized Water Reactor Fuel Spacer Grids." Nuclear Technology 139, no. 1 (2002): 72–79. http://dx.doi.org/10.13182/nt02-a3305.

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38

Chen, Xi, Sijia Du, Yu Zhang, et al. "Validation of CFD analysis for rod bundle flow test with vaned spacer grids." Annals of Nuclear Energy 109 (November 2017): 370–79. http://dx.doi.org/10.1016/j.anucene.2017.05.055.

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39

Ren, Quan-yao, Liang-ming Pan, Wen-xiong Zhou, Hang Liu, and Ting-pu Ye. "Drift-flux model of sub-channel in vertical rod bundles with spacer grids." International Journal of Heat and Mass Transfer 126 (November 2018): 946–56. http://dx.doi.org/10.1016/j.ijheatmasstransfer.2018.05.135.

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40

CHUN, Tae-Hyun, and Dong-Seok OH. "A Pressure Drop Model for Spacer Grids with and without Flow Mixing Vanes." Journal of Nuclear Science and Technology 35, no. 7 (1998): 508–10. http://dx.doi.org/10.1080/18811248.1998.9733899.

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41

Moon, Sang-Ki, Jongrok Kim, Seok Cho, et al. "Single-phase convective heat transfer enhancement by spacer grids in a rod bundle." Journal of Nuclear Science and Technology 51, no. 4 (2014): 543–57. http://dx.doi.org/10.1080/00223131.2014.881726.

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42

Kobzar, L. L., and D. A. Oleksyuk. "Experimental Studies of the Efficiency of Heat-and-Mass Transfer Intensifier Spacer-Grids." Atomic Energy 125, no. 5 (2019): 290–96. http://dx.doi.org/10.1007/s10512-019-00483-8.

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43

Saini, Nadish, and Igor A. Bolotnov. "Two-Phase Turbulence Statistics from High Fidelity Dispersed Droplet Flow Simulations in a Pressurized Water Reactor (PWR) Sub-Channel with Mixing Vanes." Fluids 6, no. 2 (2021): 72. http://dx.doi.org/10.3390/fluids6020072.

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In the dispersed flow film boiling regime (DFFB), which exists under post-LOCA (loss-of-coolant accident) conditions in pressurized water reactors (PWRs), there is a complex interplay between droplet dynamics and turbulence in the surrounding steam. Experiments have accredited particular significance to droplet collision with the spacer-grids and mixing vane structures and their consequent positive feedback to the heat transfer recorded in the immediate downstream vicinity. Enabled by high-performance computing (HPC) systems and a massively parallel finite element-based flow solver—PHASTA (Par

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44

Zavyalov, Petr. "3D Hole Inspection Using Lens with High Field Curvature." Measurement Science Review 15, no. 1 (2015): 52–57. http://dx.doi.org/10.1515/msr-2015-0008.

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Abstract One of the actual 3D measurement problems is the optical inspection of various holes. In this respect, the task of plane image formation of holes as extended 3D objects using optical methods turns out to be of primary importance. We have developed specialized lenses that perform such transformations due to specially increased aberrations (field curvature, astigmatism) for the formation of extended objects plane images. The calculations of the lens parameters are presented. The detail analysis of the imaging properties was carried out. The presented hole inspection lens has been design

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45

Yvon, Pascal, Roland Schill, Philippe Coffre, et al. "ICONE11-36205 RESULTS OF CRUSH TESTS PERFORMED ON IRRADIATED PWR ZIRCALOY-4 SPACER GRIDS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2003 (2003): 60. http://dx.doi.org/10.1299/jsmeicone.2003.60.

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46

Podila, Krishna, and Yanfei Rao. "CFD modelling of turbulent flows through 5 × 5 fuel rod bundles with spacer-grids." Annals of Nuclear Energy 97 (November 2016): 86–95. http://dx.doi.org/10.1016/j.anucene.2016.07.003.

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47

Qi, Peiyao, Xing Li, Xin Li, et al. "Experimental investigation of the turbulent flow in a rod bundle channel with spacer grids." Annals of Nuclear Energy 130 (August 2019): 142–56. http://dx.doi.org/10.1016/j.anucene.2019.02.028.

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48

Chun, Moon-Hyun, and Bub-Dong Chung. "Countercurrent flow limitation experiments with vertical multi-tube bundle with and without spacer grids." International Communications in Heat and Mass Transfer 17, no. 3 (1990): 237–45. http://dx.doi.org/10.1016/0735-1933(90)90089-3.

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49

Li, Wei, Hongjian Guo, Jing Zhang, et al. "Study on the characteristics of axial fluid excitation on fuel rods with spacer grids." Annals of Nuclear Energy 193 (December 2023): 110015. http://dx.doi.org/10.1016/j.anucene.2023.110015.

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50

Dmitriyev, Sergey M., Anton V. Gerasimov, Aleksander A. Dobrov, et al. "Experimental investigation of the coolant flow in the VVER reactor core with TVSA fuel assemblies." Nuclear Energy and Technology 7, no. (1) (2021): 49–54. https://doi.org/10.3897/nucet.7.65313.

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The paper presents the results of an experimental study to investigate the coolant interaction in adjoining fuel assemblies in the VVER reactor core composed of TVSA-T and upgraded TVSA FAs. The processes of the in-core coolant flow were simulated in a test wind tunnel. The experiments were conducted using models representing different portions of the VVER reactor core fuel bundle and consisted in measuring the radial and axial airflow velocities in representative areas within the FAs and in the interassembly space. The results of the experiments can be translated to the full-scale conditions

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