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钠冷快堆技术发展综述

杨红义 周培德 王明政 刘一哲 杨勇 颜寒 阿热爱·努尔兰

原子能科学技术2025,Vol.59Issue(z1):1-14,14.
原子能科学技术2025,Vol.59Issue(z1):1-14,14.DOI:10.7538/yzk.2025.youxian.0028

钠冷快堆技术发展综述

Comprehensive Review on Technology Development of SFRs

杨红义 1周培德 1王明政 1刘一哲 1杨勇 1颜寒 1阿热爱·努尔兰1

作者信息

  • 1. 中国原子能科学研究院,北京 102413
  • 折叠

摘要

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.

关键词

第四代核能系统/钠冷快堆/闭式燃料循环后处理/一体化快堆

Key words

generation Ⅳ reactor/sodium-cooled fast reactor/closed fuel cycle spent fuel manage-ment/integrated fast reactor

分类

核科学

引用本文复制引用

杨红义,周培德,王明政,刘一哲,杨勇,颜寒,阿热爱·努尔兰..钠冷快堆技术发展综述[J].原子能科学技术,2025,59(z1):1-14,14.

基金项目

中核集团集中研发项目 ()

原子能科学技术

OA北大核心

1000-6931

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