Fusion Engineering and Design ( IF 1.7 ) Pub Date : 2021-02-25 , DOI: 10.1016/j.fusengdes.2021.112310 H. Jin , Y. Wu , J.G. Qin , A. Vostner , J. Laquiere , M. Yu , J. Jin , B.W. Tao , H.X. Han , Q.Y. Han
ITER In-vessel coils (IVCs) are the components to be installed in the vacuum vessel for plasma positions compensation controlling. Every coil will be wound continuously and clamped through the welded Inconel 625 brackets. The coils are planned to be bolted to the rails which are welded to the vacuum vessel wall behind the blanket shield modules. The operation condition is severe for the IVC coils, combined with high radiation, high temperature, as well as the high thermal and electromagnetic loads. To make sure the safe operation, tests have been done on the mock-up coil to check its fatigue properties under the combined thermal and mechanical loads before the finalization of the design. The integrity of the mock-up coil has been evaluated after the fatigue cycling tests. In this paper, the details are presented on the test procedures and the measurement results are summarized.
中文翻译:
热和电磁载荷作用下ITER船用模型线圈的疲劳行为测试和评估
ITER容器内线圈(IVC)是要安装在真空容器中的组件,用于控制等离子体位置补偿。每个线圈将连续缠绕,并通过焊接的Inconel 625支架夹紧。线圈计划用螺栓固定在导轨上,该导轨焊接在橡皮布屏蔽模块后面的真空容器壁上。IVC线圈的工作条件非常恶劣,并伴有高辐射,高温以及高热和电磁负载。为了确保安全运行,在最终确定设计之前,已经对样机线圈进行了测试,以检查其在热和机械载荷的共同作用下的疲劳性能。样机线圈的完整性已在疲劳循环测试后进行了评估。在本文中,