钠冷快堆技术发展综述

Comprehensive Review on Technology Development of SFRs

  • 摘要: 钠冷快堆是以液态金属钠作为冷却剂的快中子核反应堆。本文系统地阐述了钠冷快堆技术的发展历程与现状。首先回顾了钠冷快堆早期在国际范围内的发展情况,探讨了第四代核能系统的核心技术概念,并对21世纪以来钠冷快堆的发展现状进行了分析;然后总结了钠冷快堆技术发展的主要趋势以及关键技术发展路线;最后对中国钠冷快堆未来的发展趋势进行了分析与展望。通过对钠冷快堆技术的系统性总结,揭示了其未来发展的方向和潜力,为后续科学研究和工程实践提供了理论支持与参考依据。

     

    Abstract: Sodium-cooled fast reactor (SFR) is an advanced nuclear reactor technology that employs fast neutrons and liquid metallic sodium as a coolant. The development history and current status of SFR technology were systematically reviewed in this paper. Firstly, the early international development of SFRs was reviewed, the core concepts of the generation Ⅳ nuclear energy systems were explored, and the development status of SFRs since the 21st century was analyzed. Secondly, the main development trends and key technological development pathways of SFR technology were summarized. Finally, an in-depth analysis and outlook for the future development trends of SFR were provided in China. Through the systematic summary of SFR technology, its future development direction and potential are revealed, providing important theoretical support and reference for subsequent engineering practices.

     

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