Design updates of a fusion superconducting conductor test facility magnet, SUCCEX

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-09 DOI:10.1016/j.fusengdes.2025.115040

Hyun Wook Kim , Hyunjung Lee , Soo-Hyeon Park , Yong Chu , Mu-yong Kim , Seokho Nam , Young Min Park , Young-Ju Lee , Jinhwan Kim , Byung Su Lim , Keeman Kim

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引用次数: 0

Abstract

The superconductor test facility, named SUperConducting Conductor Experiment (SUCCEX), is being designed since 2014 and the Korean government has lunched the official project in 2021. The SUCCEX magnet is being developed to evaluate superconducting Cable-in-Conduit Conductor (CICC) samples for the future fusion magnets. This split-pair solenoid magnet system is designed to generate magnetic fields over 15 T in a 600 mm diameter bore, with capability to test SULTAN-like conductor samples. The magnet consists of two types of coils: a high-field inner coil (IC) using high-performance Nb₃Sn strands (Jc ∼1000 A/mm² at 4.2 K, 16 T) and a low-field outer coil (OC) using ITER-grade Nb₃Sn strands (Jc >1000 A/mm² at 4.2 K, 12 T). Operating at 24.8 kA, the magnet achieves a background field of 15.4 T, enabling sample testing about 16 T when combined with sample's self-field. This paper presents recent conceptual design updates of the SUCCEX magnet, specifically focusing on the modification of the inner coil (IC) jacket thickness from 4 mm to 5 mm. The modification aims to enhance the structural integrity of the high-field conductor while maintaining the magnet's overall performance characteristics.

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核聚变超导测试设备磁体sucex的设计更新

该超导测试设施名为 "超导导体实验（SUCCEX）"，自2014年起开始设计，韩国政府已于2021年正式启动该项目。开发 SUCCEX 磁体是为了评估未来聚变磁体的超导电缆导体（CICC）样品。这种分对螺线管磁体系统设计用于在直径为 600 毫米的孔中产生 15 T 以上的磁场，能够测试类似 SULTAN 的导体样品。磁体由两类线圈组成：使用高性能 Nb3Sn 绞线的高磁场内线圈（IC）（4.2 K 时 Jc ∼1000 A/mm²，16 T）和使用 ITER 级 Nb3Sn 绞线的低磁场外线圈（OC）（4.2 K 时 Jc >1000 A/mm²，12 T）。在 24.8 kA 的工作电流下，磁体可获得 15.4 T 的背景场，结合样品的自场，可进行约 16 T 的样品测试。本文介绍了 SUCCEX 磁体的最新概念设计更新，特别侧重于将内线圈（IC）护套厚度从 4 毫米改为 5 毫米。这一修改旨在增强高场导体的结构完整性，同时保持磁体的整体性能特征。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.