Overcoming the challenges of the Future K-DEMO Superconductor Test Facility

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

Fusion Engineering and Design Pub Date : 2025-04-12 DOI:10.1016/j.fusengdes.2025.115023

Byung Su Lim , Keeman Kim , Hyun Wook Kim , Hyunjung Lee , Myounghun Kim , Jeongjeung Dang , Yong Chu

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Abstract

The test facility for high-field superconducting conductor is currently in development in Korea with the main purpose of generating an external magnetic field of up to 16 T (Tesla). This test facility will be mainly used to test superconductors intended for K-DEMO, the next-generation fusion reactor in Korea. Achieving a magnetic field intensity of up to 16 Tesla with low-temperature superconducting materials, such as Nb₃Sn, presents a significant engineering challenge. Additionally, a substantial increase in the overall costs for material and fabrication of coils has been shown. Consequently, extensive efforts have been made to address the various engineering challenges and the financial constraints. At present, the project is in the conceptual design phase to navigate through the various restrictions. Various design studies are actively progressing to generate the target magnetic field of 16 Tesla. This paper will discuss the current progress and provide the most recent technical updates concerning the construction of the future superconductor test facility.

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克服未来 K-DEMO 超导测试设备的挑战

目前，国内正在开发以产生16t（特斯拉）外磁场为主要目的的高磁场超导体试验设备。该试验设施将主要用于韩国下一代核聚变反应堆K-DEMO的超导体试验。用Nb3Sn等低温超导材料实现高达16特斯拉的磁场强度是一项重大的工程挑战。此外，材料和线圈制造的总体成本大幅增加。因此，已经作出了广泛的努力来解决各种工程挑战和财政限制。目前，该项目正处于概念设计阶段，以克服各种限制。各种设计研究正在积极进行，以产生16特斯拉的目标磁场。本文将讨论目前的进展，并提供有关未来超导体测试设施建设的最新技术更新。

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.