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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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Zhao M, Gu H. Experimental and numerical investigation on heat transfer of supercritical water flowing upward in 2 × 2 rod bundles. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110903] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107450] [Citation(s) in RCA: 16] [Impact Index Per Article: 3.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Feng W, Zhang X, Chen H. Simulation of oxygen mass transfer in fuel assemblies under flowing lead-bismuth eutectic. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2019.10.026] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Brogna C, Pucciarelli A, Ambrosini W, Razumovskiy V, Pis'mennyi E. Capabilities of high y+ wall approaches in predicting heat transfer to supercritical fluids in rod bundle geometries. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.05.053] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Critical heat flux experiments and a post-CHF heat transfer analysis using 2D inverse heat transfer. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.06.011] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Amin MM, Duan Y, He S. Large Eddy Simulation Study on Forced Convection Heat Transfer to Water at Supercritical Pressure in a Trapezoid Annulus. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2017. [DOI: 10.1115/1.4038161] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
It is now well known that heat transfer to fluid at supercritical pressure in a confined channel shows complex behaviors. This is due to the strong variations of the thermal–physical properties resulting from the changes of pressure and temperature. To improve the reliability and efficiency of the supercritical water-cooled reactors (SCWRs) to be designed, the understanding of supercritical fluid flow in the fuel assemblies is very important. The study reported here reconsiders a simplified geometry made of a trapezoid channel enclosing an inner rod to simulate the triangular arrangement of a fuel assembly. Large eddy simulation (LES) with the wall adapting local eddy viscosity (WALE) model is used to simulate the forced convection flow in the channel. Supercritical water at 25 MPa is used as the working fluid. The Reynolds number of flow based on the hydraulic diameter and the bulk velocity is 10,540, while the heat flux from the inner rod wall has been varied from 10 kW/m2 to 75 kW/m2. Large unsteady flow structures are observed to be present due to the nonuniformity of the cross section of the flow channel. The characteristics of the flow structures and their effect on the local heat transfer are analyzed using instantaneous velocities, spectrum analysis, and correlation analysis. The swinging flow structures in the wide gap are much weaker than those in the narrow gap. The behaviors of such large flow structures are influenced by the strong spatial and temporal variations of the properties. When the temperature distribution follows Tb < Tpc < Tw, the mixing parameters due to the large flow structures, including mixing coefficient and effective mixing velocity in the gap, are also significantly influenced.
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Affiliation(s)
- Muhsin Mohd Amin
- Department of Mechanical Engineering, The University of Sheffield, Sheffield S1 3JD, UK e-mail:
| | - Yu Duan
- Department of Mechanical Engineering, Imperial College London, London SW7 2AZ, UK e-mail:
| | - Shuisheng He
- Department of Mechanical Engineering, The University of Sheffield, Sheffield S1 3JD, UK e-mail:
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Bergmann CM, Ormiston SJ, Chatoorgoon V. Comparative study of turbulence model predictions of upward supercritical fluid flow in vertical rod bundle subchannels. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.06.044] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Podila K, Rao Y. CFD modelling of supercritical water flow and heat transfer in a 2 × 2 fuel rod bundle. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.03.019] [Citation(s) in RCA: 21] [Impact Index Per Article: 2.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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