期刊文献+

Preliminary design of an SCO_(2) conversion system applied to the sodium cooled fast reactor 被引量:1

原文传递
导出
摘要 The supercritical carbon dioxide(SCO_(2))Brayton cycle has become an ideal power conversion system for sodium-cooled fast reactors(SFR)due to its high efficiency,compactness,and avoidance of sodiumwater reaction.In this paper,the 1200 MWe large pool SFR(CFR1200)is used as the heat source of the system,and the sodium circuit temperature and the heat load are the operating boundaries of the cycle system.The performance of different SCO_(2) Brayton cycle systems and changes in key equipment performance are compared.The study indicates that the inter-stage cooling and recompression cycle has the best match with the heat source characteristics of the SFR,and the cycle efficiency is the highest(40.7%).Then,based on the developed system transient analysis program(FR-Sdaso),a pool-type SFR power plant system analysis model based on the inter-stage cooling and recompression cycle is established.In addition,the matching between the inter-stage cooling recompression cycle and the SFR during the load cycle of the power plant is studied.The analysis shows that when the nuclear island adopts the flow-advanced operation strategy and the carbon dioxide flowrate in the SCO_(2) power conversion system is adjusted with the goal of maintaining the sodium-carbon dioxide heat exchanger sodium side outlet temperature unchanged,the inter-stage cooling recompression cycle can match the operation of the SFR very well.
出处 《Frontiers in Energy》 SCIE CSCD 2021年第4期832-841,共10页 能源前沿(英文版)
基金 the International Cooperative Research and Development Project on Key Technologies of the Fourth Generation Nuclear Energy System Sodium-cooled Fast Reactor(2016YFE0100800).
  • 相关文献

参考文献9

二级参考文献56

  • 1张森如.主循环泵瞬态特性计算[J].核动力工程,1993,14(2):183-190. 被引量:23
  • 2刘松宇,徐济鋆.均相流蒸汽发生器瞬态分析模型[J].核动力工程,1994,15(3):230-235. 被引量:4
  • 3郭玉君,张金玲,秋穗正,苏光辉,贾斗南,喻真烷.反应堆系统冷却剂泵流量特性计算模型[J].核科学与工程,1995,15(3):220-225. 被引量:20
  • 4孙锋,夏国清,孙佳丽.新型直流蒸汽发生器的动态特性仿真研究[J].应用科技,2005,32(8):49-52. 被引量:4
  • 5DOSTAL V,DRISCOLL M J,HEJZLAR P.MIT Advanced Nuclear Power Technology Program:A supercritical carbon dioxide cycle for next generation nuclear reactors[R].USA:MIT,2004.
  • 6U.S.DOE Nuclear Energy Research Advisory Committee,the Generation Ⅳ International Forum.A technology roadmap for generation Ⅳ nuclear energy systems[R].USA:Nuclear Energy Research Advisory Committee,2002.
  • 7CHEN Yang.Novel cycles using carbon dioxide as working fluid[D].Stockholm:School of Industrial Engineering and Management,2006.
  • 8KATO Y,NITAWAKI T,MUTO Y.Medium temperature carbon dioxide gas turbine reactor[J].Nuclear Engineering and Design,2004,230:195-207.
  • 9WANG Jie,GU Yihua.Parametric studies on different gas turbine cycles for a high temperature gas-cooled reactor[J].Nuclear Engineering and Design,2005,235:1 761-1 772.
  • 10CHEN Yang.Novel cycles using carbon dioxide as working fluid[]..2006

共引文献99

同被引文献13

引证文献1

二级引证文献2

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部