Arend Nijhuis

Coupling loss optimization of central solenoid cable-in-conduit conductor for next generation fusion reactor by experiments and modeling

Yi Sun, Zichuan Guo, Jianfeng Huang, Yunhao Liu et autres

Abstract The next generation tokamak aiming to carry out D–T experiments and to demonstrate power generation, is under development at the Institution of Plasma Physics, Chinese Academy of China (ASIPP). A hybrid magnet configuration is proposed for the central solenoid (CS) coil …

cn, nl (code pays fourni par la source)

Thermal-hydraulic analysis of the CORCⓇ conductor for the DEMO CS coil

Monika Lewandowska, Aleksandra Dembkowska, Rafał Ortwein, Arend Nijhuis et autres

Conductors using High Temperature Superconductor (HTS) tapes are considered as a very promising solution for future high-field fusion magnets. Various HTS cable concepts, such as e.g. twisted stack cable, cross-conductor (CroCo), Roebel assembled coated conductor (RACC), conductor on round core (CORC Ⓡ …

pl, nl, de, us, ch (code pays fourni par la source)

Performance of the First 80 kA HTS CICC for High-Field Application in Future Fusion Reactors

Guanyu Xiao, Chao Zhou, Chuanyi Zhao, Shijie Shi et autres

A promising way to realize controlled nuclear fusion involves the use of magnetic fields to control and confine the hot plasma configuration. This approach requires superconductor magnets operating above 15 T for the next generation of fusion devices. Due to their high …

cn, ch, it, at, de, fr, nl (code pays fourni par la source)

Hysteresis loss scaling of round REBCO cable towards 20 T

Arend Nijhuis, Ruben Lubkemann, Gulio Annaballi, Huan Jin et autres

High Temperature Superconductor (HTS) cables are considered for use in tokamaks such as DEMO (EU) and Chinese next generation fusion device (CN) or compact fusion machines. HTS cables offer the advantage of increased operating temperature and field strength of the magnet coils. …

nl, cn (code pays fourni par la source)

Mechanical and electromagnetic characteristics of MgB2 wires & Cable-in-Conduit Conductors for fusion magnet application

Peng Gao, Hongjun Ma, Weijun Wang, Xintao Zhang et autres

A study on a 4-stage sub-size MgB 2 Cable-in-Conduit Conductor (CICC), tested at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP), revealed a 20% degradation in critical current at 4.2 K compared to single-strand data. To address this issue, the …

cn, nl, us (code pays fourni par la source)

Indentation Effects on Critical Performance of the New Developed WST High Jc Nb3Sn Strand

Yunhao Liu, Peng Gao, Yu Wu, Arend Nijhuis et autres

cn, nl (code pays fourni par la source)

Effect of Magnetic Field Angle, Cabling Deformation and Transverse Loading on ITER Nb3Sn Strand Hysteresis Loss

Arend Nijhuis, Mariëtte de Haan, Ruben Lubkemann, P. Bauer

For the ITER superconducting magnets, evaluation of their AC losses with computer models is essential for the preparation of the ITER magnet system commissioning and operation. A benchmarking effort on the recently tested CS Module 2 and 6 cold test AC loss …

nl, fr (code pays fourni par la source)

Local plastic deformation effects on the critical current of high-J c Nb 3 Sn strands under uniaxial strain

Yunhao Liu, Yi Sun, Peng Gao, Arend Nijhuis et autres

Abstract In order to meet the target operating parameters of the toroidal field coils (TFCs) for the next-generation Chinese compact burning plasma tokamak, high critical current density ( J c ) Nb 3 Sn strand will be applied to the high-field winding-package …

cn, nl, ch (code pays fourni par la source)

Quantitative analysis of ITER Poloidal Field joints through rigorous resistivity parameterization

Jianfeng Huang, Y. Ilyin, Yujia Zhai, Herman H.J. ten Kate et autres

Abstract The lap-type twin-box joints are integral components in International Thermonuclear Experimental Reactor (ITER) fusion magnets, with profound implications for magnet stability based on their electro-magnetic, thermal, and mechanical properties. Throughout the extensive R&D process, rigorous qualification tests are conducted to meet …

nl, fr, cn (code pays fourni par la source)

High performance of an innovative cable-in-conduit conductor with CWS cable pattern

Zichuan Guo, Yunhao Liu, Chao Dai, Arend Nijhuis et autres

Abstract Cable-in-conduit conductors, known as CICCs, were developed for constructing superconducting coils in tokamak fusion reactors. To achieve large currents in high magnetic field, CICCs were utilized with a short-twist-pitch (STP) cable pattern to prevent irreversible performance degradation, but also inducing higher …

cn, nl (code pays fourni par la source)

Studies of the CEA Design Proposals for EU-DEMO Magnets

A. Torre, C. Nguyen Thanh Dao, Q. Le Coz, P. Hertout et autres

The paper gives an overview of the latest magnet design activities at CEA for the EU-DEMO Magnet Systems. It explains the latest changes in design constraints, inputs and definitions, the updates that have been implemented in the design tools, and shows the …

fr, nl, it (code pays fourni par la source)

Impact of local plastic deformation on thermo-magnetic instability of high- J c Nb 3 Sn strand

Yunhao Liu, Yu Wu, Arend Nijhuis, Zichuan Guo et autres

Abstract The future fusion reactor devices built by Institute of Plasma Physics, Chinese Academy of Science will be a compact burning plasma facility to fill the gap between ITER and the China Fusion Engineering Test Reactor, with the mission of studying the …

cn, nl, kr (code pays fourni par la source)