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An Experimental Reversed Heat Flux Investigation of the Helium-Cooled Modular Divertor with Multiple Jets

机译:多喷射氦气冷却模块化器的实验反转热通量研究

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The Georgia Institute of Technology group has performed studies to characterize the thermal hydraulics of a single ?finger? module of the helium-cooled modular divertor with multiple jets (HEMJ) proposed for long-pulse magnetic fusion reactors in a helium (He) loop designed with maximum mass flow rate of 10?g/s. However, testing divertor modules at prototypical heat fluxes and temperatures remains an engineering challenge. A new larger helium loop with a maximum mass flow rate of 100?g/s, suitable for evaluating helium-cooled divertors with larger surface areas such as a nine-finger HEMJ module, is currently being constructed. This work presents an experimental validation of a numerical model exploring the applicability of the ?reversed heat flux approach,? which cools (versus heats) the plasma-facing surface of the divertor module to evaluate the helium-side heat transfer coefficient (HTC). The approach is to be used for performance evaluation of single and multiple modules of HEMJ in existing and future large helium loops.A cooling facility for producing a jet of water with a maximum mass flow rate of 1.4 kg/s at a maximum pressure of 0.4 MPa and temperature of 295?K (Re?=?2.2???10(5)) is described. Numerical and experimental results are presented for the heat flux and average helium impingement surface temperature over a range of water flow rates (0.5 to 1.4 kg/s) for heat fluxes as high as 5?MW/m(2).The numerical model suggests that the HTC of the water impingement surface is comparable to or greater than that of the helium impingement surface. For given helium and water temperatures, the heat flux values are generally limited by conduction across the outer shell. These initial studies provide guidance on extending this approach to estimating the thermal-hydraulic performance of larger divertor module designs while reducing the challenges associated with studying such designs in the normal heating configuration at their extremely high prototypical temperatures and incident heat fluxes.
机译:佐治亚州理工学院集团已经进行了研究,以表征单一的热水液压?具有多个喷射器(HEMJ)的氦气冷却模块化器的模块,提出用于长脉冲磁性熔接器的氦气(HE)环中的长脉冲磁性熔融反应器,其具有10Ω·克/秒的最大质量流量。然而,在原型热通量和温度下测试偏移器模块仍然是工程挑战。目前正在建造一个新的较大质量流量为100μmm质量流量为100μm的较大氦气环,适用于评估具有较大表面积的氦气冷却的偏移诸如九指针模块的较大的表面积。这项工作提出了一种探索探索的数字模型的实验验证?逆转热量通量方法,?冷却(与加热)的偏置器模块的面向等离子体表面进行了冷却(与加热),以评估氦侧传热系数(HTC)。该方法将用于现有和未来大氦气环中单个和多个模块的性能评估。冷却设施,用于生产水射流,最大质量流量为1.4 kg / s,最大压力为0.4描述了MPA和295?K的温度(RE?=?2.2 ??? 10(5))。为热通量(0.5至1.4kg / s)的热通量和平均氦冲击表面温度提出了数值和实验结果,用于热量的热量高达5?MW / m(2)。数值模型表明水冲击表面的HTC与氦冲击表面的HTC相当。对于给定的氦和水温,热通量值通常通过外壳传导限制。这些初步研究提供了延长这种方法来估算较大的偏转器模块设计的热液压性能的指导,同时减少与在其极高的原型温度和入射热通量的正常加热配置中研究这种设计相关的挑战。

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