期刊文献+

临界沸腾换热分体实验装置可行性研究

下载PDF
导出
摘要 堆内熔融物滞留策略要求压力容器下封头外表面的热流密度不能超过沸腾换热的临界热流密度(Critical Heat Flux,CHF),整体实验装置已被广泛用于强化临界沸腾换热的实验研究中,但在实际操作有局限性。本实验对比了铜光表面在分体和整体实验装置中稳态加热实验下的CHF,两者偏差整体小于1.5%。对分体实验装置进行理论误差分析,当导热硅脂厚度小于0.22mm时,误差可以控制在5%以内,分体实验装置能够有效的代替整体实验装置。
出处 《科技创新导报》 2020年第13期99-100,共2页 Science and Technology Innovation Herald
  • 相关文献

参考文献4

二级参考文献36

  • 1THEOFANOUS T G, LIU C, ADDITON S. In- vessel eoolability and retention of a core melt, DOE/ID-10460[R]. US: DOE, 1996.
  • 2JAE H P, YONG H J. An assessment method- ology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs[J]. Annals of Nuclear Energy, 2001, 28: 1 237-1 250.
  • 3REMPE J L, KNUDSON D L, ALLISON C M. Potential for AP600 in-vessel retention through ex-vessel flooding, INEEL/EXT 97-00779 [R]. US: Es. n.l, 1997.
  • 4ESMAILI H, KHATIB-RAHBAR M. Analysis of likelihood of lower head failure and ex-vessel fuel coolant interaction energetics for AP1000 [J]. Nuclear Engineering and Design, 2005, 235 1 583-1 605.
  • 5ESMAILI H, KHATIB-RAHBAR M. Analysis of in-vessel retention and ewvesseI fuel coolant interaction for AP1000, NUREG/CR-6849[R]. US: Es. n. ], 2004.
  • 6REMPE J L, KNUDSON D L, ALLISON C M, et al. Potential for AP600 in-vessel retention through ex-vessel flooding, INEEL/EXT-97 007791[R]. Idaho: Idaho National Engineering and Environmental Laboratory, 1997.
  • 7REMPE J L, KNUDSON D L. Margin for invessel retention in the APR1400-VESTA and SCDAP/RELAPS-3D analyses, INEEL/EXT-04- 02549[R]. Idaho: Idaho National Engineering and Environmental Laboratory, 2004.
  • 8THEOFANOUS T G, LIU C, ADDITON S, et al. In-vessel coolability and retention of a core melt, DOE/ID-10460[R]. Idaho:U. S. Department of Energy, 1996.
  • 9THEOFANOUS T G, MAGUIRE M, ANGELINI S, et al. The first results from the ACOPO experiment[J].. Nuclear Engineering and Design, 1997, 169(1 3): 49-57.
  • 10ESMAILI H, KHATIB-RAHBAR M. Analysis of in vessel retention and ex-vessel fuel coolant interaction for AP1000, NUREG/CR 6849 [R]. Washington D. C.: U. S. Nuclear Regulatory Commission, 2004.

共引文献11

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