A large scale research and development project for China Fusion Engineering Test Reactor (CFETR) named the comprehensive research facility for fusion technology (CRAFT) started in 2019 and is scheduled for completion in 2025. A super-conducting conductor experiment testing platform (Super-X for short) is a sub-task of CRAFT to evaluate the future supercon-ducting part performance. The maximum testing magnetic field at bore center is 15 T, the dimensions of testing space are 100 × 160 × 550 mm, the field homogeneity of testing space is superior to 95%, and the maximum testing current is 100 kA. The direct current (DC) magnet is the key sub-system for the facility provid-ing the background magnetic field. The engineering design for DC magnet has been accomplished in the middle of this year, and its technical parameters meet the required. The main work focus-es on the structural design of the split coils, the axial preload and the hanging assembly. This paper presents the progress on the engineering design of the DC magnet.

The insulation system is an important part of the fusion magnet coils and its role is to mechanically support, insulate, fix, and protect superconducting magnets. The insulation materials used for the China Fusion Engineering Test Reactor (CFETR) Central Solenoid Model Coil (CSMC) are glass-fiber reinforced plastics. Internal defects may be generated in the composite insulation structure during manufacture or service life. The inspection of the composites has many difficulties, mainly due to the multiple interfaces and different elastic properties. This paper investigated the microstructure of the insulation system and defined the test objects for non-destructive test(NDE). Phased array ultrasonic test (PAUT) technology was developed to evaluate the integrity of the insulation system.

The Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) has announced a project to design a 14 T MRI magnet with a 900 mm warm bore and comprised of Nb ₃ Sn Rutherford cables, the homogeneity of the magnetic field is better than 0.5 ppm in a 22 cm diameter spherical volume. The diameter of main coil is about 4 m and the total weight is about to 130 tons. This article describes structural design of 14 T MRI suspension system. A global finite element model is created based on the design geometry data to investigate the mechanical property of the suspension system under the seismic load.

AbstractChina Fusion Engineering Test Reactor (CFETR), a new tokamak device, is under concept design based on the expe-rience of Experimental Advanced Superconducting Tokamak (EAST) and ITER. Research and development of TF coil for CFETR is carried out by ASIPP. TF coil is winding by Cable in-Conduit Conductor (CICC). Main manufacturing process of CICC includes welding of jacket, draw lead, winding and global helium gas tightness test. After winding, the diameter of TF con-ductor is about 4 m and the weight is about to 30 t. This paper describes structural design of dewar which is used for the global helium gas tightness test for the TF conductor after winding. A global finite element model is created based on the design geome-try data to investigate the mechanical property of the dewar un-der static load and seismic load. Index TermsCFETR, TF coil, dewar, mechanical analysis, seismic performance analysis

Feasibility study of ITER In-vessel coils bracket manufacture and integration had been developed in Institute of Plasma Physics, Chinese Academy of Sciences. The ITER In-Vessel Coil system is comprised of Edge-Localized Mode (ELM) and Vertical Stabilization (VS) coils. The ELM coils are used to mitigate the Edge Localized Modes and the VS coils are used to provide Vertical Stabilization of the plasma. Designed bracket for IVC coils is a kind of building block type three or four stacked components with arcuate groove matching with round conductor. This paper describes structure design, manufacture and integration process of the ELM and VS bracket. R&D of bracket weld and assembly sequence optimization are carried out to determine the welding and assembly process. At last, three brackets are integrated in ASIPP.

The Comprehensive Research Facility for Fusion Technology (CRAFT) is a big platform dedicated to advancing key technologies and conducting performance tests on critical components of fusion energy reactors. It comprises 20 specialized test facilities and 4 auxiliary systems. Among these, the NDE (Non-Destructive Examination) laboratory is a sub-system of the SC (Superconducting) test facility, which is one of the 20 core facilities. The laboratory integrates phased array ultrasonic testing (PAUT, 0.5 MHz∼15 MHz), high-frequency acoustic microscopy (up to 100 MHz), digital radiography, and multi-scale X-ray computed tomography (micro-XCT up to 300 kV and high-penetration XCT up to 9 MeV). In addition, a dedicated cryogenic ultrasonic testing system has been developed, enabling defect inspection under temperatures ranging from −196°C to 150°C. Specialized NDE methodologies have been established for cable-in-conduit conductors (CICC), brazed joints in in-vessel components, and superconducting structural assemblies. Furthermore, an intelligent defect recognition algorithm based on a multi-round cross-modal attention mechanism has been implemented, achieving an accuracy of 99.25% in weld defect classification. The developed platform has been successfully applied in ITER, BEST, and CRAFT engineering projects, demonstrating its effectiveness in ensuring structural integrity and reliability of superconducting fusion components.