Numerical analysis on supercritical water heat transfer in a 2 × 2 rod bundle

Xiong, Juntao; Xu, Cheng; Yang, Yanhua

doi:10.1016/j.anucene.2015.02.005

Cited by 17 publications

(2 citation statements)

References 39 publications

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“…Moreover, many studies devoted to the heat transfer performance of supercritical fluid. Xiong et al (Xiong and Cheng, 2014;Xiong et al, 2015) proposed a four-equation model to predict the mixed convective heat transfer in supercritical pressure fluid and assessed the performance of RANS models in predicting supercritical pressure heat transfer in a 2 × 2 rod bundle. Castro et al (2020) performed coupled calculations with the CFD code CFX-19.0 and the Monte Carlo neutronic code MCNP6 to analyze the heat transfer in supercritical water flowing through the typical fuel assembly of the high-performance light water reactor (HPLWR).…”

Section: Introductionmentioning

confidence: 99%

Optimization of a Fuel Assembly for Supercritical Water-Cooled Reactor CSR1000

et al. 2021

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As one of the Generation IV nuclear reactors, the SCWR (supercritical water-cooled reactor) has high economy and safety margin, good mechanical properties for its high thermal efficiency, and simplified structure design. As the key component of nuclear reactor, the fuel assembly has always been the main issue for the design of the SCWR. The design of the fuel assembly for CSR1000 proposed by the Nuclear Power Institute of China (NPIC) has been optimized and presented in this study, which is composed of four subassemblies welded by four filler strips and guide thimbles arranged close together in the cross-shaped passage. Aiming at improving the hydraulic buffer performance of the cruciform control rod, the scram time and terminal velocity of control rod assembly were calculated to assess the scram performance based on the computational fluid dynamics and dynamic mesh method, and the mechanical property and neutronic performance of assemblies were also investigated. It has been demonstrated that the optimized fuel assembly had good feasibility and performance, which was a promising design for CSR1000.

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Section: Introductionmentioning

confidence: 99%

Optimization of a Fuel Assembly for Supercritical Water-Cooled Reactor CSR1000

et al. 2021

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“…In addition, flow instability has also been observed in other nonuniform channel flows [13][14][15][16][17][18][19]. An experimental validation study of 2 Â 2 rod bundle conducted by Xiong et al [20] used the x-Reynolds stress model and baseline-Reynolds stress model. The models were found to be capable of predicting the cross flow pattern in between subchannels.…”

Section: Introductionmentioning

confidence: 99%

Large Eddy Simulation Study on Forced Convection Heat Transfer to Water at Supercritical Pressure in a Trapezoid Annulus

Amin

Duan

2017

Journal of Nuclear Engineering and Radiation Science

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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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