Conveners
Thu-Mo-Po4.04 - Fusion VII: Joints and Terminations
- Boris Stepanov (EPFL)
- Louis ZANI (CEA-IRFM)
In order to develop and verify the key techniques and manufacturing process of the full-size central solenoid (CS) coil for China fusion engineering test reactor (CFETR), the central solenoid model coil (CSMC) project has been launched in the Institute of Plasma and Physics, Chinese Academy of Sciences (ASIPP). The CFETR CS model coil is a hybrid superconducting magnet of 12 T maximum magnetic...
High-temperature superconductors (HTS) are promising candidates for use in the high-field magnets needed in thermal nuclear fusion reactors. Their high critical temperatures allow them to operate at temperatures far above 4 K and ease requirements on nuclear heat generation and heating during ramping of the magnetic field. Other benefits compared to low-temperature superconductors include...
Joint resistances of eight short samples have been measured until 2018 as a qualification test for ITER Toroidal Field (TF) coils. The joint sample consists of two short TF conductors with the length of 1.535 m, and each conductor has two joint boxes at both ends. The lower joint is a testing part that is full size joint of the TF coil. The upper joint is connected to 100 kA current leads of a...
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...
The ITER Central Solenoid Modules (CSM) are being fabricated at General Atomics (GA) at their Poway, CA Magnet Technologies Center. Each of the seven modules will undergo final testing at the GA facility to demonstrate their performance with full current of 48.5 kA, 11 T and at 4.5 K. In order to perform tests on multiple modules, a demountable coaxial joint using indium wires was developed to...
Abstract: In the superconducting magnets system of the International Thermonuclear Experimental Reactor (ITER) project, the heater chains are used to avoid heavy condensation or ice formation on the current leads of feeder. As an insulating and heat-conducting component, the heater chains should satisfy electrical insulation and thermal conduction properties at the same time. Due to no...
The ITER Central Solenoid (CS) has terminal butt-type joints called Coaxial joints. It was decided to study a design of this joint with rutherford shunts, and to build models for its resistive and inductive behaviors. In particular, the behavior of the joint under magnetic field transients is investigated with various analytical models that are compared with a FEM model. The key point of the...
