Enhanced thermal stability and irradiation resistance of ODS-W/CuCrZr joints by interlayer employ and interface improvement

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-04-10 DOI:10.1016/j.jnucmat.2025.155818

Dang Xu , Changcheng Sang , Kaichao Fu , Ruizhi Chen , Pengqi Chen , Yingwei Lu , Dahuan Zhu , Qiu Xu , Jigui Cheng

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引用次数: 0

Abstract

To enhance the performance of W/Cu divertor materials under high-temperature and irradiation conditions, this study utilizes oxide dispersion-strengthened tungsten (ODS-W) and CuCrZr alloy as base materials. A tri-layer ODS-W/W-50Cu/CuCrZr joint was fabricated using spark plasma sintering (SPS), incorporating a nanoporous surface treatment on the ODS-W surface and a W-50Cu interlayer between ODS-W and CuCrZr. The effects of the surface treatment and W-50Cu interlayer on the microstructure, mechanical properties, and irradiation resistance of the joints were systematically investigated. Results demonstrate that the nanoporous structure significantly enhances interfacial bonding, achieving a tensile strength of 227.6 MPa and a ductility of 5.82 %. Fracture analysis reveals a transition in failure mode. Fractures shift from the ODS-W/Cu interface to the W-50Cu interlayer, accompanied by a transition from brittle to ductile fracture behavior. The W-50Cu interlayer effectively mitigates the mismatch in thermal expansion and minimizes stress concentrations, thereby enhancing interfacial stability at elevated temperatures while maintaining excellent thermal conductivity and mechanical properties. Under irradiation, the W-50Cu interlayer acts as a “trap”, capturing and neutralizing irradiation-induced defects. This mechanism reduces interfacial damage, mitigates hardening, and improves irradiation stability. These findings establish a framework for optimizing W/Cu divertor material design for high-temperature and irradiation-intensive applications.

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通过层间和界面改进，提高了ODS-W/CuCrZr接头的热稳定性和耐辐照性

为了提高钨/铜导流器材料在高温和辐照条件下的性能，本研究采用氧化物弥散增强钨（ODS-W）和CuCrZr合金作为基材。采用火花等离子烧结（SPS）技术，在ODS-W表面进行纳米孔处理，并在ODS-W和CuCrZr之间添加W-50Cu中间层，制备了ODS-W/W-50Cu/CuCrZr三层复合材料。系统研究了表面处理和W-50Cu中间层对接头组织、力学性能和耐辐照性能的影响。结果表明，纳米孔结构显著增强了界面结合，拉伸强度达到227.6 MPa，延展性达到5.82%。断裂分析揭示了破坏模式的转变。断口由ODS-W/Cu界面向W-50Cu界面转变，断裂行为由脆性向韧性转变。W-50Cu夹层有效缓解了热膨胀失配，减小了应力集中，从而提高了界面在高温下的稳定性，同时保持了优异的导热性和机械性能。在辐照下，W-50Cu中间层作为一个“陷阱”，捕获和中和辐照引起的缺陷。这种机制减少了界面损伤，减轻了硬化，提高了辐照稳定性。这些发现为优化高温和辐射密集型应用的钨/铜导流器材料设计建立了框架。

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

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.