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Qu W, Xie H, Shen D, Wang Z, Xiong J. Experimental study of coherent structures downstream mixing vaned spacer grid of different inclination angles in a 5 × 5 rod bundle by TR-PIV. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109516] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Orosz GI, Magyar B, Szerbák D, Kacz D, Aszódi A. ALLEGRO Gas cooled Fast Reactor Rod Bundle investigations with CFD and PIV method. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.112062] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Verification and validation of CFD and its application in PWR fuel assembly. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104485] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]
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Mikuž B, Roelofs F. Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2022. [DOI: 10.1115/1.4051446] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Abstract
Reproduction of turbulent flow and heat transfer inside a pressurized water reactor (PWR) fuel assembly is a challenging task due to the complex geometry and the huge computational domain. Capability of a wall-modeled Reynolds-averaged Navier–Stokes (RANS) simulation approach has been examined, which had already been validated against the measurements of the MATiS-H experiment. The method is here expanded to a larger computational domain aiming to reproduce flow and thermal field in the entire PWR fuel assembly. Namely, in the first part of this study, wall-modeled RANS is performed in a relatively short section of the representative PWR fuel assembly containing one single mixing grid with an array of 15 × 15 fuel rods. Linear and nonlinear eddy-viscosity turbulence models have been applied; however no significant difference is observed in the predicted pressure drop in the fuel assembly. The obtained predictions revealed an interesting pattern of swirl flow as well as diagonal cross flow downstream the mixing grid, which is driven by the applied design of split-type mixing vanes. In the second part, the computational model is extended to a domain representative of a complete PWR fuel assembly with ten mixing grids, inlet and outlet sections. Pressure drop and flow field are analyzed together with the predicted temperature and potential hot spots. In spite of a relatively coarse spatial resolution of the applied approach, the wall-modeled RANS provided promising results at least for the qualitative prediction of the pressure, flow field, and location of hot spots.
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Affiliation(s)
- B. Mikuž
- Nuclear Research and Consultancy Group, Westerduinweg 3, Petten 1755 LE, The Netherlands;Reactor Engineering Division, Jožef Stefan Institute, Jamova cesta 39, Ljubljana 1000, Slovenia
| | - F. Roelofs
- Nuclear Research and Consultancy Group, Westerduinweg 3, Petten 1755 LE, The Netherlands
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Orosz GI, Aszódi A. CFD modelling of mixing vane spacer grids for ALLEGRO relevant gas cooled reactor fuel geometry. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108628] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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LES and URANS study on turbulent flow through 3 × 3 rod bundle with spacer grid and mixing vanes using spectral element method. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108474] [Citation(s) in RCA: 7] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Calorimeter conceptual design for Neutral Beam Injector of DTT - CFD optimisation and thermal stress analysis. FUSION ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.fusengdes.2021.112469] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2020.02.020] [Citation(s) in RCA: 9] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Dhurandhar SK, Sinha SL, Verma SK. Effects of Mixing Vane Spacer on Flow and Thermal Behavior of Fluid in Fuel Channels of Nuclear Reactors—A Review. NUCL TECHNOL 2020. [DOI: 10.1080/00295450.2019.1698257] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
Affiliation(s)
- Satish Kumar Dhurandhar
- National Institute of Technology Raipur, Mechanical Engineering Department, Raipur(C.G.)- 492010, India
| | - S. L. Sinha
- National Institute of Technology Raipur, Mechanical Engineering Department, Raipur(C.G.)- 492010, India
| | - Shashi Kant Verma
- Institute for Plasma Research, Cryopump & Pellet Injector Division and Advanced Computer Simulation Group, Gandhinagar-382428, Gujarat, India
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Tas-Koehler S, Lecrivain G, Krepper E, Unger S, Hampel U. Numerical investigation on the effect of transversal fluid field deformation on heat transfer in a rod bundle with mixing vanes. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110575] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Karaman U, Kocar C, Rau A, Kim S. Numerical investigation of flow characteristics through simple support grids in a 1 x 3 rod bundle. NUCLEAR ENGINEERING AND TECHNOLOGY 2019. [DOI: 10.1016/j.net.2019.06.020] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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