Houxiang Han

Ceramic array armor suffers from insufficient constrained capability of ceramic units in the embedded armor structure, leading to weak interfacial bonding at ceramic unit connections, significantly reducing the overall ballistic performance. In this study, centimeter-sized SiC hexagonal prisms and micrometer-sized B4C powders were used as reinforcing materials. A high-strength, high-toughness, and multiscale array (SiCh-p + B4Cp)/5083Al armor with strong interfacial bonding was prepared using pressure infiltration technique. The (SiCh-p + B4Cp)/5083Al armor was combined with ultra-high molecular weight polyethylene and 6252 armor steel to form an integrated armor system. To investigate the effect of constrained material on its ballistic performance, the array structures with epoxy and 5083Al as constrained material were prepared for comparison. Ballistic performance tests were conducted using 12.7 mm Armor-Piercing Incendiary (API). The damage mechanisms of the armor structure were studied through finite element simulation and a combination of macroscopic and microscopic analyses. The results demonstrate excellent overall ballistic performance of the (SiCh-p + B4Cp)/5083Al armor system. The high-strength and high-toughness 55 vol%B4Cp/5083Al composite material exhibits strong interfacial bonding with SiCh-p, providing robust support to the SiCh-p. The armor back deformation was reduced by 50 %, and the ceramic layer dissipated more than 70 % of projectile kinetic energy, The materials prepared in this study exhibit significant potential in ballistic performance.

In order to verify key techniques and manufacturing aspects of the central solenoid (CS) coil of the China fusion engineering test reactor (CFETR), the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP) plan to develop a CS model coil. The conceptual design of the CS model coil of CFETR has been carried out by ASIPP. The CS model coil shall produce a 12-T peak field in the bore of the magnet. The maximum magnetic field change rate is 1.5 T/s. The designed operating current is 47.65 kA. The CFETR CS model coil structure design mainly includes coil winding design, buffer zone design, preload structure design, coil joints and joint supports design, and liquid helium cooling channels design. This paper presents the conceptual design of CFETR CS model coil structure based on electromagnetic design and optimization.

A central solenoid model coil (CSMC) is being developed to verify the large-scale Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn superconducting coil manufacture technologies for China Fusion Engineering Test Reactor in ASIPP (Institute of Plasma Physics, Chinese Academy of Sciences). The CSMC composed of Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn and NbTi hybrid superconducting magnet can reach to the maximum magnetic field 12 T. All of the Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn and NbTi coils are composed of pancakes windings, pancake joggles, and upper and lower leads. For the multipancakes, the radial dimensions are from 1500 to 3544.8 mm and the maximum axial height is 1545.4 mm. High manufacture accuracy must be acquired for coil continuous winding, i.e., the innermost and outermost circular turn surface profile tolerance is 2 mm and the conductor feeding tolerance is 0.5 <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">0</sup> / <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">00</sub> L. The winding R&D activities, including the continuous winding for the pancakes and the online forming for the joggles, have been conducted to optimize and finalize the coil design as well as to carry out the coil winding technology verification and improvement. Now, the continuous winding for double pancakes of the Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn inner coil has been finished. The details have been described in this paper.

The engineering design of the China Fusion Engineering Test Reactor (CFETR) has been completed in 2020. A largescale R&D project for CFETR named the comprehensive research facility for fusion technology (CRAFT) was initiated in Sep. 2019. As a sub-task of the CRAFT, a superconducting experiment testing platform (Super-X for short) is planned to be constructed for evaluating the future superconducting parts performance. Its main technical parameter includes: the background field of 15 T, the dimensions of testing space of 100 × 160 × 550 mm, the field homogeneity of testing space ≥ 95%, and the maximum testing current of 100 kA. For now, the preliminary design for Super-X has been accomplished. The DC magnet provides the background magnetic field for Super-X. It is a kind of split coil that includes two symmetrical coils assemblies. The innermost diameter is about 644 mm, the outermost diameter is 2874 mm. Each coil assembly is composed of three concentric Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn coils. The peak field is 15.7 T and the field homogeneity reach to 98.2%. The high field coil (HFC) and medium field coil (MFC) is typically dominated by high-J <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">c</sub> Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn cable-in-conduit conductor (CICC), and the low field coil (LFC) by ITER grade Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn CICC. This paper presents the preliminary design of the background DC magnet system (BM).