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Steady-state transverse heat transfer in a single channel CICC

机译:单声道CICC中的稳态横向热传递

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Current mathematical models and numerical codes used for thermal-hydraulic analyses of forced-flow superconducting cables used in the fusion technology, such as, e.g. Cable-in-Conduit Conductors (CICCs), are typically 1D. They demand reliable constitutive expressions for the transverse momentum, energy and optionally also mass transport processes occurring between different parallel conductor components, in order to reliably simulate the behavior of any superconducting magnet design either at normal operating conditions or during a quench evolution. Energy transport processes can effectively be expressed using heat transfer coefficient (HTC) and the considered wetted perimeter/surface. Only few HTC correlations for flow in a CICC bundle have been proposed in the literature, but none of them is widely accepted for predictive use. As a result, in thermalhydraulic studies of conductors designed for the EU-DEMO coils standard heat transfer correlations for flows in smooth tubes are utilized, although they do not seem very appropriate for CICCs. Systematic measurements of heat transfer coefficients in a CICC bundle should be conducted to provide an experimental database for further trials to develop a reliable predictive heat transfer correlation. In the present work we report the results of measurements of the steady-state HTC between a jacket wall and demineralised water flowing (i) in a smooth tube and (ii) in a CICC bundle of the reference sample (JT60-SA TF conductor). The measurements were carried out at the THETIS installation. We used four values of water inlet temperature, in the range 30-68 degrees C, and various mass flow rates, in the range 0.15 - 0.40 kg/s, to obtain the results in possibly wide range of Pr and Re numbers. The experimental values of HTC for CICC slightly increased with the mass flow rate from about 7500 to 9400 W/(m(2).K) in the considered Re range (890-3490) and were almost independent on temperature. The performed experiment was also simulated with the THEA code for additional validation of the obtained HTC values.
机译:用于融合技术中使用的强制流动超导电缆的热液压分析的电流数学模型和数值码,例如,例如,导管导管导体(CICC)通常为1D。它们要求在不同平行导体部件之间发生横向动量,能量和可选的质量传输过程的可靠组成表达式,以便可靠地模拟在正常操作条件下或在骤冷进化期间的任何超导磁体设计的行为。能量传输过程可以使用传热系数(HTC)和考虑的湿润周边/表面有效地表达。在文献中提出了CICC束中的流量的少数HTC相关性,但是它们都不被广泛接受预测使用。结果,在为欧盟 - 演示线圈设计的导体的热液压研究中,使用了平滑管中流动的传热相关性,但它们似乎对CICC似乎并不适合。应进行CICC束中的热传递系数的系统测量,以提供实验数据库,以便进行可靠的预测传热相关性。在本工作中,我们在参考样品(JT60-SA TF导线的CICC束中。测量是在θ安装的情况下进行的。我们使用了四个进水温度的值,在30-68摄氏度的范围内,以及各种质量流量,范围为0.15-0.40 kg / s,以获得可能宽范围的PR和RE编号的结果。 CICC的HTC的实验值略微增加,大约7500至9400 w /(m(2).k)中的大约7500-9400 w /(m(2).k)在考虑的re范围(890-3490)中,几乎独立于温度。还使用THEA代码模拟所进行的实验,以额外验证获得的HTC值。

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