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Kumar G, Singh RK. Supercritical water flow in heated wire wrapped rod bundle channels: A review. PROGRESS IN NUCLEAR ENERGY 2023. [DOI: 10.1016/j.pnucene.2023.104620] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/23/2023]
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Hou J, Song Q, Leng H, Xue C, Yuan Y, Zhou Y. A non-destructive model for thermal-hydraulics of wire-wrapped rod bundle and wire-rod contact corner microscopic behavior. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104469] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/05/2022]
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Kiss A, Mervay B. Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2020. [DOI: 10.1115/1.4046842] [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
The application of relatively simple and cheap wrapped wire spacer in the European supercritical water-cooled reactor (SCWR) (high-performance light water reactor (HPLWR)) has been proposed in order to provide enhanced heat transfer in the fuel assembly without unacceptable penalty in pressure loss. The wires cause twisting flow in the fuel assembly, which means the coolant not only flows straight in the axial direction but also has a significant transverse velocity component, and strong mixing between neighboring subchannels occurs. The aim of this ongoing research is to numerically investigate the effect of wrapped wire spacers on thermal hydraulics of the turbulent coolant flow and its heat transfer in a small bundle of four fuel rods. One bare and six-wired geometries with varying wire pitches (1–6 turn(s) of wires) have been studied. It was found that the wires generate significant amount of transverse velocity, decrease the wall temperature, and increase the heat transfer coefficient mostly in corner subchannels which were the hottest in bare geometry. Thus, the presence of wires enhances heat transfer where it is most needed. Temperature hot spots with moderate values have been identified on the cladding wall of fuel rods. Based on the results, a technically optimal choice of number of wire turns from thermal hydraulic sense has been proposed.
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Affiliation(s)
- Attila Kiss
- Department of Nuclear Techniques, Institute of Nuclear Techniques (NTI), Budapest University of Technology and Economics (BME), Muegyetem rkp. 9, R bld. 317/7a, Budapest 1111, Hungary
| | - Bence Mervay
- Department of Nuclear Energetics, Institute of Nuclear Techniques (NTI), Budapest University of Technology and Economics (BME), Muegyetem rkp. 9, R bld. 317/7a, Budapest 1111, Hungary
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Kiss A, Mervay B. Numerical analysis on the thermal hydraulic effect of wrapped wire spacer in a four rod fuel bundle. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2018.11.024] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Kiss A, Churkin A, Pilkhwal DS, Vaidya AM, Ambrosini W, Pucciarelli A, Podila K, Rao Y, Leung L, Yuzhou C, Anderson M, Zhao M. Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2017. [DOI: 10.1115/1.4038162] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Two computational fluid dynamic (CFD) benchmarks have been performed to assess the prediction accuracy and sensitivity of CFD codes for heat transfer in different geometries. The first benchmark focused on heat transfer to water in a tube (first benchmark), while the second benchmark covered heat transfer to water in two different channel geometries (second benchmark) at supercritical pressures. In the first round with the experimental data unknown to the participants (i.e., blind calculations), CFD calculations were conducted with initial boundary conditions and simpler CFD models. After assessment against measurements, the calculations were repeated with the refined boundary conditions and material properties in the follow-up calculation phase. Overall, the CFD codes seem to be able to capture the general trend of heat transfer in the tube and the annular channel but further improvements are required in order to enhance the prediction accuracy. Finally, sensitivity analyses on the numerical mesh and the boundary conditions were performed. It was found that the prediction accuracy has not been improved with the introduction of finer meshes and the effect of mass flux on the result is the strongest among various investigated boundary conditions.
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Affiliation(s)
- Attila Kiss
- Institute of Nuclear Techniques, Budapest University of Technology and Economics, Muegyetem rkp. 9., Budapest 1111, Hungary e-mail:
| | - Andrey Churkin
- OKB GIDROPRESS, Ordzhonikidze Str. 21., Podolsk 142103, Russian Federation e-mail:
| | | | | | - Walter Ambrosini
- Faculty of Engineering, Department of Mechanical Engineering, Nuclear Engineering and Production, University of Pisa, Via Diotisalvi, 2, Pisa I-56126, Italy e-mail:
| | - Andrea Pucciarelli
- Faculty of Engineering, Department of Mechanical Engineering, Nuclear Engineering and Production, University of Pisa, Via Diotisalvi, 2, Pisa I-56126, Italy e-mail:
| | - Krishna Podila
- Canadian Nuclear Laboratories, Chalk River K0J 1J0, ON, Canada e-mail:
| | - Yanfei Rao
- Canadian Nuclear Laboratories, Chalk River K0J 1J0, ON, Canada e-mail:
| | - Laurence Leung
- Canadian Nuclear Laboratories, Chalk River K0J 1J0, ON, Canada e-mail:
| | - Chen Yuzhou
- China Institute of Atomic Energy, P.O. Box 275(59), Beijing 102413, China e-mails:
| | - Mark Anderson
- Department of Engineering Physics, University of Wisconsin-Madison, 1500 Engineering Dr., Madison, WI 53706 e-mail:
| | - Meng Zhao
- Institute of Fusion and Reactor Technology (IFRT), Karlsruhe Institute of Technology (KIT), Kaiserstraße 12, Gebäude 07.08, Karlsruhe 76131, Germany e-mail:
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