Numerical simulation of heat transfer improvement in the divertor of fusion reactors by using Al2O3 nanofluid

Ashouri, Hadighe; Ghasemizad, A.; Sadatkiae, Seyyed Mahmoud; Seddighzade, Asghar

doi:10.1007/s40094-018-0315-y

Cited by 3 publications

(1 citation statement)

References 38 publications

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“…Zhang et al [27] predicted CHF based on the rapid increase of local wall temperature with ANSYS FLUENT. Ashouri et al [28] numerically investigated turbulent force convective heat transfer of water-based Al 2 O 3 nanofluid flowing through the CuCrZr cooling tube of a small scale of mock up made of five tungsten monoblocks using single phase model. Koncar et al [29] have done much work to validate NEPTUNE_CFD through several DNB experiments.…”

Section: Cfd Simulation Resultsmentioning

confidence: 99%

Critical heat flux analysis of divertor cooling flow channel in fusion reactor with CFD method

Wang

Guo

et al. 2022

THERM SCI

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Situated at the bottom of the vacuum vessel, the divertor extracts heat and ash produced by the fusion reaction, minimizes plasma contamination, and protects the surrounding walls from thermal and neutronic loads. The vertical targets of divertor are designed to be able for up to 20 MW/m2 high heat flux. It is a great ordeal for both the material performance and the cooling ability. Critical heat flux (CHF) margin is very crucial during the design of divertor. ANSYS FLUENT is used in this paper to predict the CHF on a monoblock structure with a twisted tape inside the tube. Numerical results are validated with the corresponding sets of experimental results. In this paper, CFD method used to predict CHF of divertor cooling channel was first introduced. On the other hand, influence of inlet subcooling on CHF is studied in detail. The inlet subcooling affect the CHF much complicated for the single- side heated and swirl flow channel. Whether the influencing trend or the locations of CHF occurrence are different under different inlet subcooling. The derivations between the simulation and experimental results were no more than 32%. This study proves the CFD tools can provide efficient help on the understanding of the CHF phenomenon of complex construction.

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Section: Cfd Simulation Resultsmentioning

confidence: 99%

Critical heat flux analysis of divertor cooling flow channel in fusion reactor with CFD method

Wang

Guo

et al. 2022

THERM SCI

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ANSYS-CFX simulation of the SRBTL test loop core with nanofluid coolant

et al. 2021

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In the present study, CFD calculations are presented for the three types of water-based nanofluids Al2O3/water, CuO/water and TiO2/water with 0.1% volume fraction. These calculations are done with ANSYS-CFX and as geometry the SRBTL test loop as scaled down test loop for a VVER-1000 reactor core design is used. The goal of this study is to evaluate the CFD program against the SRBTL test loop core as a scaled core for applying water-based nanofluids as coolant. ANSYS-CFX simulation data are validated against the RELAP5/MOD3.2 simulation data for pure water. This comparison shows a good agreement. The simulation results for the nanofluids and water including Re number, temperature, viscosity, pressure drop and heat transfer coefficient through the SRBTL test loop core are compared. The results of the comparisons show that the SRBTL test loop core is suitable to extract experimental data of water-based nanofluids for using them as coolant in the VVER-1000 reactor.

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Preliminary Design of a Heat Pipe-Cooled Blanket for CFETR

Wang

Guo

2021

Energies

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Blankets are a difficult problem for fusion engineering design. Because of the complex flow channels, the design, production, processing, and accident maintenance of blankets are all huge challenges for traditional water/gas-cooled blankets. Blankets are the bridge for heat transfer and tritium production. A high-performance blanket with simplified structure is obviously beneficial for engineering, safety, and the economy. In this study, gravity heat pipes instead of coolant flow channels are adopted to remove the heat. Compared with coolant-cooled systems, heat pipes may be simpler and more reliable. The in-vessel and in-box loss of coolant accident (LOCA) will not occur because there is no coolant in the blanket. Moreover, a damaged heat pipe may be replaced easily compared to a damaged water-cooled blanket. In this study, a hypothetical heat pipe-cooled blanket for the China Fusion Engineering Test Reactor (CFETR) was proposed and one module of the blanket was analyzed by numerical simulation. The results were compared with those of a water-cooled blanket, and the temperature distribution of the heat pipe-cooled blanket is more uniform. This study verified the preliminary feasibility of heat pipe-cooled blankets and provided a fresh idea for blanket design.

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Numerical simulation of heat transfer improvement in the divertor of fusion reactors by using Al2O3 nanofluid

Cited by 3 publications

References 38 publications

Critical heat flux analysis of divertor cooling flow channel in fusion reactor with CFD method

Critical heat flux analysis of divertor cooling flow channel in fusion reactor with CFD method

ANSYS-CFX simulation of the SRBTL test loop core with nanofluid coolant

Preliminary Design of a Heat Pipe-Cooled Blanket for CFETR

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