Microstructural and mechanical analyses of YBCO coated conductor tapes in high-irradiation environments

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-02-01 Epub Date: 2025-01-13 DOI:10.1016/j.fusengdes.2025.114802
Yuanzhou Pan , Canjie Xin , Wei Wu , Mingzhi Guan , Xingzhe Wang
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Abstract

Upgrading the superconducting magnets in the High Energy Fragment Separator (HFRS) at the High Intensity Heavy Ion Accelerator Facility (HIAF) is challenging due to the complex irradiation field. YBCO coated conductor (CC) tapes in magnets are designed to resist high radiation heat loads and endure significant irradiation doses. However, prolonged operation will also result in degradation of the tapes. To assess the reliability of the superconducting magnets, it's crucial to study the microstructures and macro-behaviors of YBCO conductors subjected to higher irradiation doses. In this work, irradiation experiments were conducted using 160 MeV 40Ar ions on YBCO conductors with/without Cu stabilizer, ranging from 4.8 × 107 ions/cm2 to 4.8 × 1012 ions/cm2. Micro-defects morphology analysis employed scanning electron microscopy (SEM), energy-dispersive x-ray spectroscopy (EDS) and transmission electron microscopy (TEM). Macro-measurements of unirradiated and irradiated YBCO conductors were conducted to investigate the irradiation dose dependence of superconducting properties and mechanical behaviors. Post high-dose irradiation, TEM and EDS analyses revealed YBCO CC tapes without Cu stabilizer exhibited more obvious delamination behaviors at the edge of YBCO layer due to the irradiation defects. Macro-behavior measurements indicated nonlinear dependencies of mechanical properties, critiical current (Ic) and critical tenperature (Tc) on irradiation fluences. Furthermore, for the purpose of comparison, tapes with Cu stabilizer demonstrated superior radiation-resistant properties than those without Cu stabilizer, and the mechanical parameters and superconducting behaviors of YBCO CC tapes without Cu stabilizer significantly degraded at high irradiation dose, thus, the irradiation damages in YBCO layer identified as the primary cause of Ic and Tc degradation under high irradiation fluence.
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高辐照环境下YBCO涂层导体带的显微组织和力学分析
高强度重离子加速器(HIAF)高能碎片分离器(HFRS)超导磁体的升级由于辐照场复杂而具有挑战性。磁体中的YBCO涂层导体(CC)带设计用于抵抗高辐射热负荷并承受显著的辐照剂量。但是,长时间的操作也会导致磁带的劣化。为了评估超导磁体的可靠性,研究高辐照剂量下YBCO导体的微观结构和宏观行为至关重要。本文采用160 MeV 40Ar离子对有/无Cu稳定剂的YBCO导体进行辐照实验,辐照范围为4.8 × 107 ~ 4.8 × 1012离子/cm2。采用扫描电镜(SEM)、能量色散x射线能谱(EDS)和透射电镜(TEM)对微缺陷进行形貌分析。对未辐照和辐照后的YBCO导体进行了宏观测量,研究了其超导性能和力学行为与辐照剂量的关系。高剂量辐照后,TEM和EDS分析表明,由于辐照缺陷,未添加Cu稳定剂的YBCO CC带在YBCO层边缘表现出更明显的分层行为。宏观行为测量表明,辐照影响下的力学性能、临界电流(Ic)和临界温度(Tc)呈非线性关系。此外,为了比较,添加Cu稳定剂的带的耐辐射性能优于未添加Cu稳定剂的带,并且未添加Cu稳定剂的YBCO CC带的力学参数和超导行为在高辐照剂量下明显退化,因此,YBCO层的辐照损伤被认为是高辐照通量下Ic和Tc降解的主要原因。
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来源期刊
Fusion Engineering and Design
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.
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