Experimental Study on Transient Heat Transfer for Helium Gas Flowing in a Minichannel

Feng Xu, Qiusheng Liu, S. Kawaguchi, M. Shibahara
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引用次数: 1

Abstract

The blanket modules of first wall need bear tremendous heat flux due to the very high temperature of plasma in the nuclear fusion reactor. Therefore, it is significant to clarify the knowledge of transient heat transfer process for helium gas flowing in the tubes installed in the blanket modules. In this research, the transient heat transfer process of turbulent forced convection for helium gas flowing in a horizontal minichannel was experimentally investigated. The test tube made of platinum with the inner diameter of 1.8 mm, the wall thickness of 0.1 mm and the effective length of 90 mm was heated by a direct current from power source. The heat generation rate of the test tube, Q̇, was raised with an exponential function, Q̇ = Q0 exp(t/τ), where Q0 is the initial heat generation rate, t is time, and τ is e-folding time of heat generation rate. The heat generation rates of the test tube were controlled and measured by a heat input control system. The flow rates were adjusted by the bypass of gas loop and measured by the turbine flow meter. The experiment was conducted under the e-folding time of heat generation rate ranged from 40 ms to 15 s. Based on experimental data, it is obvious that the heat flux and temperature difference between surface temperature of test tube and bulk temperature of helium gas increased with the exponentially increasing of heat generation rate. At the same flow velocity, the heat transfer coefficients approached constant values when the e-folding time is longer than about 1 s (quasi-steady state), but increased with a decrease of e-folding time when the e-folding time is smaller than about 1 s (transient state). The heat transfer coefficients increased with the increase in flow velocities but showed less dependent on flow velocities at shorter e-folding time. Furthermore, the Nusselt number under quasi-steady and transient condition was affected by the Reynolds number and the Fourier number.
氦气在小通道内流动的瞬态传热实验研究
由于核聚变反应堆内等离子体温度极高,第一壁包层模块需要承受巨大的热流。因此,阐明包层模块内氦气管内流动的瞬态传热过程具有重要意义。实验研究了氦气在水平小通道内紊流强制对流的瞬态换热过程。将内径为1.8 mm,壁厚为0.1 mm,有效长度为90 mm的铂制成的试管用直流电源加热。试管产热率Q()以指数函数Q () = Q0 exp(t/τ)提高,其中Q0为初始产热率,t为时间,τ为产热率的e折叠时间。通过热输入控制系统对试管的产热率进行控制和测量。通过气路旁通调节流量,用涡轮流量计测量流量。实验在生热速率为40 ms ~ 15 s的电子折叠时间下进行。实验数据表明,随着产热率呈指数级增加,氦气的热流密度和试管表面温度与本体温度之间的温差明显增大。在相同流速下,当电子折叠时间大于1 s左右(准稳态)时,传热系数趋于恒定,而当电子折叠时间小于1 s左右(瞬态)时,传热系数随电子折叠时间的减小而增大。换热系数随流动速度的增加而增加,但在较短的电子折叠时间内对流动速度的依赖较小。准稳态和瞬态条件下的努塞尔数受雷诺数和傅里叶数的影响。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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