Validation of Helium Inlet Design for ITER Toroidal Field Coil

被引:3
作者
Boyer, C. [1 ]
Seo, K. [1 ]
Hamada, K. [1 ]
Foussat, A. [1 ]
Le Rest, M. [1 ]
Mitchell, N. [1 ]
Decool, P. [2 ]
Savary, F. [3 ]
Sgobba, S. [3 ]
Weiss, K-P [4 ]
机构
[1] ITER Org, F-13115 St Paul Les Durance, France
[2] CEA, Ctr Cadarache, F-13108 St Paul Les Durance, France
[3] CERN, European Org Nucl Res, CH-1211 Geneva, Switzerland
[4] KIT, D-76344 Eggenstein Leopoldshafen, Germany
关键词
Fatigue; fusion reactor design; superconducting coil; toroidal magnetic field;
D O I
10.1109/TASC.2013.2293845
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
The ITER organization has performed design and its validation tests on a helium inlet structure for the ITER Toroidal Field (TF) coil under collaboration with CERN, KIT, and CEA-Cadarache. Detailed structural analysis was performed in order to optimize the weld shape. A fatigue resistant design on the fillet weld between the shell covers and the jacket is an important point on the helium inlet structure. A weld filler material was selected based on tensile test at liquid helium temperature after Nb3Sn reaction heat treatment. To validate the design of the weld joint, fatigue tests at 7 K were performed using heat-treated butt weld samples. A pressure drop measurement of a helium inlet mock-up was performed by using nitrogen gas at room temperature in order to confirm uniform flow distribution and pressure drop characteristic. These tests have validated the helium inlet design. Based on the validation, Japanese and European Union domestic agencies, which have responsibilities of the TF coil procurement, are preparing the helium inlet mock-up for a qualification test.
引用
收藏
页数:4
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