Qualification of ITER PF6 helium inlet
Autor: | Guang Shen, Shuangsong Du, C. Sborchia, Yuntao Song, Huan Wu, Weiyue Wu, Jijun Xin, Kevin Smith, P. Readman, Wei Wen |
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Rok vydání: | 2018 |
Předmět: |
geography
Materials science Tokamak geography.geographical_feature_category Mechanical Engineering Nuclear engineering chemistry.chemical_element Temperature cycling Welding Inlet 01 natural sciences 010305 fluids & plasmas law.invention Nuclear Energy and Engineering chemistry law Electromagnetic coil Magnet 0103 physical sciences General Materials Science 010306 general physics Cooling down Helium Civil and Structural Engineering |
Zdroj: | Fusion Engineering and Design. 134:1-4 |
ISSN: | 0920-3796 |
Popis: | The Poloidal Field (PF) coils are one of the main sub-systems of the ITER magnets. The PF6 coil is being manufactured by the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) as per the Poloidal Field coils cooperation agreement signed between ASIPP and Fusion for Energy (F4E). As one of the critical components, helium inlet locates on the innermost turn and supplies the coil with supercritical helium. During Tokamak operation, the helium inlet will undergo huge cyclic electromagnetic loads and thermal cycling during cooling down and warming up. This paper focus on the main steps of ITER PF6 helium inlet qualification. Helium inlet hole drilling and stainless steel wrapping removal were firstly been carried out. Helium inlet welding with full penetration by automatic welding machine was then performed, followed by leak proof test, non-destructive test, fatigue test and tomography test. At the end, the samples were sectioned for micro and macro inspection. The results show ITER PF6 helium inlet qualification has successfully met the requirements of PF procurement agreement(PA) and was approved by ITER IO. |
Databáze: | OpenAIRE |
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