事故容错燃料碳化硅包壳表面临界热流密度特性机理研究

11805149
2018
A2803.反应堆物理与技术
张魁
青年科学基金项目
副教授
西安交通大学
27万元
微液层;碳化硅包壳;事故容错燃料;临界热流密度;界面行为
2019-01-01到2021-12-31
  • 中英文摘要
  • 结题摘要
  • 结题报告
  • 项目成果
  • 项目参与人
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序号 标题 类型 作者
1 Experimental investigations on single-phase convection and two-phase flow boiling heat transfer in an inclined rod bundle 期刊论文 Zhang K.;Hou Y. D.;Tian W. X.;Zhang Y. P.;Su G. H.;Qiu S. Z.
2 Experimental investigations on leak flow rate characteristics of water through axial artificial microcracks of steam generator tubes under back pressure conditions 期刊论文 Zhang K.;You H. B.;Zhou Y. K.;Zhao X. H.;Zhang J.;Hou Y. D.;Tian W. X.;Su G. H.;Qiu S. Z.
3 Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic 期刊论文 Zhang K.;Xie X. F.;Yang T. A.;Li X. Y.;Chen R. H.;Tian W. X.;Su G. H.;Qiu S. Z.
4 Experimental study on leak flow rate characteristics of high pressure subcooled water through axial and circumferential microcracks of steam generator tubes under high back pressure conditions 期刊论文 Zhang K.;Shi Y. G.;You H. B.;Zhao X. H.;Tian W. X.;Su G. H.;Qiu S. Z.
5 Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor 期刊论文 Zhang K.;Yang T. A.;Liao H. Y.;Xie X. F.;Chen R. H.;Tian W. X.;Su G. H.;Qiu S. Z.
6 Experimental investigations on single-phase convection and critical heat flux in vertical tubes under oscillatory flow condition 期刊论文 Zhang K.;Huang Y. J.;You H. B.;Tian W. X.;Su G. H.;Qiu S. Z.
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