Design Optimization and Assessment of Fabrication of ITER Central Solenoid Twin Box Joints

The ITER Central Solenoid (CS) will be one of the world's largest and most powerful pulsed superconducting electromagnet ever built; at an approximate weight of 1300 tons and a total height of 18 m consisting of a stack of six electrically independent 4.1 m diameter modules. In order to electri...

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Bibliographic Details
Published inIEEE transactions on applied superconductivity Vol. 30; no. 4; pp. 1 - 4
Main Authors Aviles Santillana, Ignacio, Guinchard, Michael, Lourenco, Sandra Sophie, Motschmann, Fritz, de Frutos, Oscar Sacristan, Sgobba, Stefano, Bruton, Andrew, Gaxiola, Enrique, Libeyre, Paul, Schild, Thierry, Decool, Patrick
Format Journal Article
LanguageEnglish
Published New York IEEE 01.06.2020
The Institute of Electrical and Electronics Engineers, Inc. (IEEE)
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Summary:The ITER Central Solenoid (CS) will be one of the world's largest and most powerful pulsed superconducting electromagnet ever built; at an approximate weight of 1300 tons and a total height of 18 m consisting of a stack of six electrically independent 4.1 m diameter modules. In order to electrically connect the CS with the feeder busbars, 12 twin box joints are used to assure an efficient high current transfer while avoiding excessive AC losses. The fabrication of the box entails a succession of steps: explosion bonding of the stainless steel and the copper, precision machining of the internal part of the box and the cover, introduction of the conductor bundle followed by a controlled compaction to achieve the required void fraction, closure welding the cover onto the box, and subsequent reaction heat treatment (HT) for the formation of the Nb3Sn superconductor. The combined effect of all these fabrication processes, if not optimized, can lead to significant residual stresses and large localized plastic deformation acting during HT, which have empirically shown to result into microstructural heterogeneities and in the worst cases, cracking, and thereby component disqualification for use into a nuclear environment. The paper summarizes design optimizations investigated through mock-ups and could be implemented to remedy the present manufacturing fabrication technology process qualification failure(s). Various solutions have been realized by changing different design parameters whose effect on the response to the HT is studied. Dimensional metrology and residual stress measurements via hole - drilling method complemented with metallographic investigations were performed to assess the suitability of each of the solutions. Additionally, an innovative test bench is described, that was implemented for in - situ monitoring of a twin box mock ups during HT.
ISSN:1051-8223
1558-2515
DOI:10.1109/TASC.2020.2970663