摘要
钠冷快堆是第四代先进核能系统的首选堆型,它具有可增殖核燃料、嬗变放射性废物以及高热效率发电等优势.超临界二氧化碳布雷顿循环具有热效率高、结构紧凑、消除钠和水化学反应风险等优点,是第四代核能系统推荐的革新型动力转换方式之一.本文对超临界二氧化碳循环在钠冷快堆中的应用进行研究,采用理论分析、试验研究以及开发软件的方法,对超临界二氧化碳循环用于钠冷快堆带来的热工水力、钠-超临界二氧化碳反应、系统设计及分析模拟工具等关键技术问题进行了分析研究,结果表明超临界二氧化碳循环可消除传统钠冷快堆的钠水反应问题,提高钠冷快堆的安全性,同时超临界二氧化碳循环一定程度上还可以提高钠冷快堆的经济性,作为第四代钠冷快堆动力转换方案具有重要优势和良好的工程可行性.
Sodium-cooled fast reactor,which is an important direction of advanced nuclear technology because of breeding ability,transmutation ability,and high thermal efficiency,is a priority of Generation IV nuclear systems.Supercritical carbon dioxide(SCO_(2))Brayton cycle is an innovative power conversion option that has been suggested by the Generation IV International Forum because of high thermal efficiency and compact structure,etc.Key technologies in the application of SCO_(2)to sodium-cooled fast reactors,which include SCO_(2)thermal hydraulics,sodium/(SCO_(2))reaction,conversion system design and simulations,are introduced in this paper along with research plan,research method and results.The results show that the SCO_(2)power cycle deserves further research as part of Generation IV sodium-cooled fast reactors,because the application could improve safety and economy by eliminating sodium-water reaction and improving thermal efficiency.
作者
杨红义
杨晓燕
张东旭
徐迟
杨军
赵民富
YANG HongYi;YANG XiaoYan;ZHANG DongXu;XU Chi;YANG Jun;ZHAO MinFu(China Institute of Atomic Energy,Beijing 102413,China)
出处
《中国科学：技术科学》
EI
CSCD
北大核心
2021年第3期324-340,共17页
Scientia Sinica(Technologica)
关键词
钠冷快堆
超临界二氧化碳动力转换
热工水力
仿真模拟
sodium cooled fast reactor
supercritical CO_(2)power conversion system
thermal hydraulics
simulation
