大规模生产用于 DEMO 聚变反应堆岔流器的氧化物分散强化铜合金的可行性研究

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-06-05 DOI:10.1016/j.jnucmat.2024.155205
Hao Yu , Toshiki Saito , Zimo Gao , Yasuyuki Ogino , Sosuke Kondo , Ryuta Kasada , Hiroyuki Noto , Yoshimitsu Hishinuma , Suguru Matsuzaki
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引用次数: 0

摘要

氧化物分散强化铜(ODS 铜)合金具有很大的潜力,可用作 DEMO 聚变反应堆岔流系统的散热材料。考虑到它们未来在聚变反应堆岔流系统中的应用,必须大规模生产 ODS 铜合金。本研究的目的是与钢铁制造商 Kobelco 研究所合作,在已经建立的 ODS 铁合金大规模生产工艺的基础上,通过改进生产工艺,研究大规模生产 ODS 铜合金的可行性。在对机械合金化(MA)参数进行优化后,成功实现了 ODS 铜粉末的大规模生产,回收率超过 90%,使用循环水冷却的工业级减速器球磨机一次批量生产约 1 千克粉末。该研究对批量生产的 ODS 铜合金进行了全面的表征,包括力学性能、微观结构和热扩散率,并在此基础上提出了低能球磨的新概念,以实现 ODS 铜合金的批量生产。
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Feasibility study on mass-production of oxide dispersion strengthened Cu alloys for the divertor of DEMO fusion reactor

Oxide dispersion strengthened Cu (ODS Cu) alloys possess a high potential to be used as promising heat sink materials for the divertor system in DEMO fusion reactors. Considering their future application in fusion reactor divertor systems, mass-production of ODS Cu alloys is a must. The purpose of this study is to investigate the feasibility of large-scale production of ODS Cu alloys by improving the production process based on the already established mass-production process of ODS Fe alloys in cooperation with the steel manufacturer Kobelco Research Institute. After optimization of the mechanical alloying (MA) parameters, a large-scale production of ODS Cu powders was successfully achieved with a recovery rate of over 90% and around 1Kg powder in one batch production using an industry-level attritor ball mill cooled by circulating water. The mass-produced ODS Cu alloys were comprehensively characterized, including mechanical properties, microstructure and thermal diffusivity, and a new concept of low-energy ball milling was proposed based on the results to realize the mass-production of ODS Cu alloys.

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来源期刊
Journal of Nuclear Materials
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.
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