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Validation of the 4C Thermal-Hydraulic Code Against 25 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC)

机译:在ITER环形场模型线圈(TFMC)中针对25 kA安全放电验证4C热工液压代码

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摘要

The first step of the validation of the recently developed thermal-hydraulic code 4C is presented. We study the transient evolution during a so-called standard 25 kA safety discharge of the International Thermonuclear Experimental Reactor (ITER) Toroidal Field Model Coil (TFMC), tested in 2001–2002 in the TOSKA facility at the Karlsruhe Institute of Technology, Germany. The computed outlet He temperatures from both winding and case cooling channels, as well as the local maximum temperature increase of the structures, are shown to be in good agreement with the measured data.
机译:介绍了验证最新开发的热工代码4C的第一步。我们研究了国际热核实验堆(ITER)环形场模型线圈(TFMC)在所谓的标准25 kA安全放电期间的瞬态演化,该过程在2001-2002年在德国卡尔斯鲁厄技术学院的TOSKA设施中进行了测试。计算得出的来自绕组和壳体冷却通道的出口He温度,以及结构的局部最大温度升高都与实测数据非常吻合。

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