期刊文献+

超临界二氧化碳部分冷却布雷顿循环参数优化 被引量:3

Parameters Optimization of a Supercritical CO_2 Partial Pre-cooling Brayton Cycle
下载PDF
导出
摘要 针对一级再热超临界二氧化碳部分冷却布雷顿循环建立循环热力学模型,分析循环关键参数对循环热效率的影响。结果表明:最佳再热压力的最佳值约为第一级透平的0.5倍;在给定条件下,使压缩机入口参数接近于临界值、减小夹点温差、提高透平入口温度、提高压缩机效率和透平效率都可以提高循环热效率;透平效率对循环热效率的影响大于压缩机效率对循环热效率的影响。 A thermodynamic model was established for the single-reheat supercritical COz (S-CO2) partial pre-cooling Brayton cycle, so as to study the effects of key cycle parameters on the thermal efficiency of the cycle. Results show that the reheat pressure exists an optimal value, which is about 0.5 times of the first turbine inlet pressure. Under given conditions, the cycle thermal efficiency could be increased by making the inlet parameters of the compressor be close to its critical value, decreasing the pinch point temperature difference, increasing the turbine's inlet temperature, or increasing the efficiency of the turbine and the compressor, etc. Moreover, it can be found that the influence of the turbine efficiency on the cycle thermal efficiency is greater than that of the compressor efficiency.
出处 《发电设备》 2018年第1期7-10,18,共5页 Power Equipment
关键词 超临界二氧化碳 部分冷却 布雷顿循环 循环热效率 supercritical CO2 partial pre-cooling Brayton cycle cycle thermal efficiency
  • 相关文献

参考文献5

二级参考文献34

  • 1糜洪元.国内外燃气轮机发电技术的发展现况与展望[J].电力设备,2006,7(10):8-10. 被引量:36
  • 2HuangYanping(黄彦平),WangJunfeng(王俊峰).Applications of supercritical carbon dioxide in nuclear reactor system [J]. Nuclear Power Engineering , 2012, 33 (3): 21 -27.
  • 3CHEN Yang.Novel cycles using carbon dioxide as working fluid[]..2006
  • 4Dostal V.A supercritical carbon dioxide cycle for next generation nuclear reactors[]..2004
  • 5KATO Y,NITAWAKI T,MUTO Y.Medium temperature carbon dioxide gas turbine reactor[].Nuclear Engineer The.2004
  • 6WANG Jie,GU Yihua.Parametric studies ondifferent gas turbine cycles for a high temperaturegas-cooled reactor[].Nuclear Engineering and Design.2005
  • 7US Department of Energy.A technology roadmap for generation IV nuclear energy systems. GIF002-00 . 2002
  • 8DOE. A technology roadmap for generation IV nuclear energy systems[R]. US : DOM, 2002.
  • 9Dostal V,Driscoll M J, Hejzlar P. A supercritical carbon dioxide cycle for next generation nuclear reactors, MIT- ANP-TR-100[R]. Massachusetts : MIT, 2004.
  • 10Hejzlar P,Dostal V,Driscoll M J,et al. Assessment of gas cooled fast reactor with indirect supereritical CO2 cycle [J]. Nuclear Engineering and Technology (Special Issue on ICAPP 05) ,2006,38(2) :109-118.

共引文献92

同被引文献18

引证文献3

二级引证文献8

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