Development of joints in Eurpoe for the ITER TFMC

机译：为欧洲TFMC开发欧洲关节

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The feasibility of the superconducting coils of the International Thermonuclear Experimental Reactor (ITER) Toroidal Field (TF) magnet will be demonstrated by the manufacture and test of the Toroidal Field Model Coil (TFMC). This model coil uses a Nb_3Sn conductor, wound in pancakes, the electrical connection between which is achieved by overlap joints using the twin-box concept. The development program relies on the manufacture of three full-size joint samples to be tested in the Europen test facility SULTAN at CRPP in Villingen (Switzerland). Mock-ups have been built to assess design options. Implementation in the TFMC has been supported by detailed finite element analyses of the joint area.

机译：通过对环形磁场模型线圈（TFMC）的制造和测试，将通过制造和测试来证明国际热核实验反应器（ITER）环形磁铁（TF）磁铁的超导线圈的可行性。该模型线圈采用Nb_3Sn导体，在薄煎饼中缠绕，电连接在使用双箱概念的重叠接头之间实现。发展方案依赖于在Villingen（瑞士）的CRPP在CRPP的苏丹在欧洲测试设施苏丹进行测试的三种全尺寸关节样本的制造。模拟了模拟以评估设计选项。通过联合区域的详细有限元分析支持TFMC中的实现。

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《International conference on magnet technology》|1998年||共4页
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P.Libeyre; D.Ciazynki; P.Decool; E.Salpietro R.Maix; H.Fillunger; A.Bonito Oliva; B.Crepel; R.Kreutz;
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中图分类磁性材料、铁氧体;
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1. Thermal-Hydraulic Simulation of 80 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC) Using the 4C Code [J] . Savoldi Richard L., Bonifetto R., Heller R., Plasma Science, IEEE Transactions on . 2012,第3期

机译：使用4C代码在ITER环形场模型线圈（TFMC）中对80 kA安全放电进行热工液压仿真
2. Validation of the 4C Thermal-Hydraulic Code Against 25 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC) [J] . Zanino R., Bonifetto R., Heller R., Applied Superconductivity, IEEE Transactions on . 2011,第3期

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
3. Axial compression test on ITER-TFMC conductors at room temperature [J] . H. Fillunger, R.K. Maix, R. Prokopec, Fusion Engineering and Design . 2009,第2a6期

机译：在室温下对ITER-TFMC导体进行轴向压缩测试
4. Development of joints in Eurpoe for the ITER TFMC [C] . P.Libeyre, D.Ciazynki, P.Decool, International conference on magnet technology;MT-15 . 1998

机译：在欧洲为ITER TFMC开发接头
5. Developments of joint elements and solution algorithms for dynamic analysis of jointed structures. [D] . Yue, Xue. 2002

机译：节理结构动态分析的节理单元和求解算法的发展。
6. Development of in-vessel components of the microfission chamber for ITER [O] . M. Ishikawa, T. Kondoh, K. Ookawa, -1

机译：用于ITER的微裂变室的容器内组件的开发
7. Report on the annual accounts of the European Joint Undertaking for ITER and the Development of Fusion Energy for the financial year 2011 together with the replies of the Joint Undertaking [O] . 2011

机译：关于2011年财政年度欧洲ITER联合承诺和聚变能源发展年度报告的报告连同联合承诺的回复
8. TFMC Tcs Data: How do We Compare Conductor Performance to the Strand and What Conclusions for ITER We May Draw [R] . Martovetsky, N. 2003

机译：TFmC Tcs数据：我们如何将导体性能与strand进行比较以及我们可能得出的ITER结论

Development of joints in Eurpoe for the ITER TFMC

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