Examination of ITER Central Solenoid prototype joints Articles uri icon

authors

  • AVILES SANTILLANA, I.
  • SGOBBA, S.
  • CASTILLO RIVERO, S.
  • FERNANDEZ PISON, MARIA DEL PILAR
  • LIBEYRE, P.
  • EVERITT, D.
  • MARTOVETSKY, N.

publication date

  • December 2018

start page

  • 157

end page

  • 161

volume

  • 146, Part A

International Standard Serial Number (ISSN)

  • 0920-3796

Electronic International Standard Serial Number (EISSN)

  • 1873-7196

abstract

  • The ITER Magnet System will be the largest and most challenging integrated superconducting magnet system ever built. For the Central Solenoid (CS), cable - in - conduit - conductors (CICCs) of nearly one kilometre length are produced, but still, it will be necessary to connect several lengths together to wind the gigantic 110 tonnes coils. The creation of these superconducting joints is one of the most delicate parts of the assembly. There are three types of ITER CS joints: splice joints, coaxial joints and twin-box joints. US ITER, the ITER Domestic Agency of the USA produced a prototype containing all three types of joints. The goal is to test the performance of the joints in the SULTAN facility of the Swiss Plasma Center (SPC), capable of reproducing close - to - service conditions: high magnetic field (up to T background field), high current (up to 100kA) and high mass flow rate of supercritical helium for cooling. The paper describes the results of a comprehensive examination campaign aimed at understanding the relation between fabrication and performance of the CS prototype joints. The test campaign combines advanced image analysis for the assessment of the void fraction of the conductors with Scanning Electron Microscopy (SEM) and energy dispersive X-ray spectroscopy (EDS) to evaluate the quality of the contact between the strands and the sleeve / sole of the joints.

subjects

  • Mechanical Engineering

keywords

  • central solenoid; joints; csjus1; fabrication; performance