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Volume 56 期 3,2026 2026年第56卷第3期
  • Intelligent Nuclear, Additive Future

    MI Zhengpeng, FU Guozhong, YU Zeyuan, HE Gening, WANG Yuyang, CHENG Yue

    DOI:10.7512/j.issn.1001-2303.2026.03.01
    摘要:Additive manufacturing (AM) is hailed as a core technology leading the Fourth Industrial Revolution. The innovative R&D and application advancement of AM have become a central focus in high-tech competition. Nuclear energy, as a safe, economical, and efficient clean energy source, can effectively support China's national strategy of "Carbon Peak and Carbon Neutrality." The application of AM in the nuclear energy sector holds significant importance. This study first reviews the current development of AM technologies globally and domestically, followed by an analysis of typical AM research cases in China's nuclear energy field. Based on this, it systematically outlines the research and application value of AM in nuclear energy. Combining global and domestic AM trends, the study identifies key technologies for the next phase of AM research in nuclear energy and proposes recommendations to further advance AM applications in China's nuclear sector.  
    关键词:nuclear power;additive manufacturing;development suggestion;research status   
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    更新时间:2026-04-01

    HOU Mingdong, MAO Hu, ZHANG Zhenxing, WANG Jing, PENG Sijie, DING Xiaolin

    DOI:10.7512/j.issn.1001-2303.2026.03.02
    摘要:In recent years, the application of additive manufacturing technology in the nuclear field has gained increasing research attention, with some additively manufactured components already being deployed in operational nuclear power plants. This article provides a comprehensive review of the progress in the application of additive manufacturing technology in the nuclear sector, analyzes existing challenges and issues, and systematically summarizes relevant content. Additive manufacturing, which builds components layer by layer, overcomes the geometric limitations of traditional processes and offers advantages such as rapid prototyping, material performance optimization, integrated manufacturing of complex structures, and in-service repair for nuclear applications, demonstrating significant potential. Currently, a global pattern of "two major leaders, China and the United States, with multiple countries pursuing distinctive development paths" has emerged in nuclear additive manufacturing. The technological pathways span from prototype validation to engineering applications, gradually transforming the research, development, and manufacturing paradigms of nuclear energy equipment. Despite the progress made in the application of additive manufacturing technology in the nuclear field, its widespread adoption still faces practical challenges, such as material performance and long-term reliability issues, process defects and quality control difficulties, and lagging regulatory and standards systems. Nuclear-grade equipment and critical components are subjected to long-term service conditions involving high temperatures, high pressure, and radiation. A thorough understanding of their high-temperature mechanical performance data is essential. However, there is a scarcity of long-term performance data for additively manufactured materials under radiation conditions. Nanoscale precipitates, anisotropy, and micro-voids generated during the additive manufacturing process can become sources of irradiation-assisted corrosion cracking under radiation, thereby affecting the service life of nuclear-grade equipment and components and posing safety risks. Consequently, engineering applications of additively manufactured parts require post-processing such as hot isostatic pressing or high-temperature solution annealing to induce recrystallization and microstructural homogenization. Furthermore, current nuclear safety regulations do not explicitly address the certification of additively manufactured nuclear-grade equipment and components, resulting in gaps in regulatory coverage. Existing domestic and international standards systems for the nuclear field have yet to fully encompass additive manufacturing equipment and components, particularly in areas such as material acceptance and process qualification. The certification of nuclear-grade additively manufactured equipment currently relies on case-by-case reviews, and equipment licensing, safety analysis, and evaluation must be conducted individually based on project-specific characteristics.  
    关键词:nuclear industry;additive manufacturing;progress in applications;nuclear-grade equipment and components;material properties;nondestructive testing   
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    更新时间:2026-04-01

    YU Hao

    DOI:10.7512/j.issn.1001-2303.2026.03.03
    摘要:Nuclear-grade heat exchangers based on additive manufacturing technology can significantly enhance heat exchange efficiency while reducing the volume and weight by microchannel design and structural optimization, providing crucial technical support for the compact design and performance improvement of pool-type reactors. However, the complex internal cavity surfaces present critical challenges for engineering applications, including surface roughness defects(initial Ra 10-15μm)caused by the Selective Laser Melting (SLM) process and difficulties in polishing high-aspect-ratio flow channels. Focusing on the design requirements of nuclear-grade heat exchangers for pool-type reactors, the difficulties and specifications for treating high-aspect-ratio microchannel heat exchange surfaces are analyzed. A systematic review was conducted on the research progress in polishing techniques for complex internal structures, including mechanical polishing, abrasive flow polishing, laser polishing, magnetic abrasive flow polishing, and electrochemical polishing. The suitability of different processes is compared and analyzed based on core performance indicators such as surface roughness, contamination control, material integrity, and geometric adaptability. An abrasive flow-electrochemical composite polishing process is recommended, which can effectively balances polishing efficiency with structural integrity. However, key issues still need to be addressed, such as the optimization of heat exchanger structural design compatibility, the development of refined process specifications, the prevention of cross-contamination and assurance of cleanliness in media, and non-destructive testing technology for complex internal cavities. This study provides an important reference for the selection and optimization of surface treatment technologies for nuclear-grade heat exchangers.  
    关键词:additive manufacturing;nuclear-grade heat exchanger;reactor;complex internal cavity surface;polishing   
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    更新时间:2026-04-01

    WEN Weiying, QI Huan, LI Qingyu, LIAO Zhen, ZHANG Yabin, MA Zhaodandan

    DOI:10.7512/j.issn.1001-2303.2026.03.04
    摘要:Critical nuclear power components operating in extreme environments characterized by high temperature, high pressure, and intense irradiation are susceptible to severe wear, necessitating the development of surface strengthening coatings with superior wear resistance. Laser additive manufacturing, distinguished by its rapid solidification and controllable heat input, offers an effective pathway for optimizing the microstructure and enhancing the performance of Fe-based composite coatings. This study investigates the comparative microstructural evolution and properties of Fe-based composite coatings fabricated via Extreme High-Speed Laser Cladding (EHLA) and Broadband Laser Cladding (EH-BLC). The results indicate that EH-BLC, benefiting from a more uniform energy distribution and a higher cooling rate, facilitates the formation of planar interlayer interfaces, a narrowed heat-affected zone (HAZ), and a refined equiaxed grain structure. Concurrently, the EH-BLC coating establishes a continuous and dense carbide network, whereas the EHLA coating is characterized by skeletal defects and fragmentation. Attributed to this intact and refined microstructure, the EH-BLC coating demonstrates a low and stable coefficient of friction (COF) along with reduced wear depth. Consequently, the dominant wear mechanism transitions from brittle spalling to mild ploughing and stable plastic flow. Furthermore, the EH-BLC coating exhibits superior electrochemical performance, evidenced by a higher corrosion potential, a lower corrosion current density, and enhanced pitting resistance. Therefore, by constructing a microstructure featuring refined grains and a continuous hard-phase network, the EH-BLC process significantly enhances both wear and corrosion resistance, providing a reliable processing route for the engineering application of high-performance coatings on critical nuclear components.  
    关键词:nuclear power key components;laser additive manufacturing;Fe-based composite coating;wear resistance;corrosion resistance   
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    更新时间:2026-04-01
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