期刊文献+

HFETR自然循环能力分析研究 被引量:1

Analysis and Research on Natural Circulation Capacity of HFETR
下载PDF
导出
摘要 针对高通量工程试验堆(HFETR)的运行特点,本文利用RELAP5/MOD3程序对HFETR进行了数值建模,并结合反应堆实际运行工况,采取了阶跃升功率法和积分功率法分析了系统压力和压力壳平均水温对HFETR最大自然循环能力的影响。结果表明:系统在常压和带压工况下,HFETR的最大自然循环能力分别为0.9、2.0MW。自然循环能力随运行压力的升高而增大,随压力壳水温的升高而降低。本文基于计算数据与理论推导提出了预测不同平均水温下最大自然循环能力的关系式,该公式具有指导反应堆实际运行的工程意义。 For the operating characteristics of HFETR, the numerical model of HFETR was established by RELAP5/MOD3 to analysis the maximal natural circulation capacity. Combining with the reactor running condition, the influence of the system pressure was analyzed by ascending power in step method and the pool water temperature on natural circulation characteristics was analyzed by integral power method. The results show that the natural circulation capacity are 0.9 and 2.0 MW separately under low pressure and high pressure , the natural circulation capacity increases as the running pressure increases, however the natural circulation capacity decreases as the coolant temperature increases in the pressure vessel. Based on the computational result and the theoretical deduction,a correlation was proposed to predicate the relationship between the natural circulation mass flow and the core power under different coolant temperatures.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2010年第B09期198-203,共6页 Atomic Energy Science and Technology
关键词 高通量工程试验堆 系统压力 平均水温 自然循环能力 HFETR system pressure average coolant temperature natural circulationcapacity
  • 相关文献

参考文献3

二级参考文献12

  • 1任功祖,动力反应堆热工水力分析,1982年
  • 2杨世铭.传热学[M].北京:高等教育出版社,1987..
  • 3徐济鋆.沸腾传热与气液两相流[M].北京:原子能出版社,2001..
  • 4Ramsom VH.RELAP/MOD2 Code Manual,Vol.1,Code Structure,Systems Models,and Solution Method[S].NUREG/CR-4312,EGG-2396,EG & G Idaho Inc.1985.
  • 5黄彦平.压水反应堆自然循环特性研究[D].西安:西安交通大学博士学位论文,2003.
  • 6Jiang Shengyao.Conversion From Single to Two-Phase Operation in a Natural Circulation Nuclear Reactor[J].Kerntechnik,1998,63:132 ~ 138.
  • 7Sudo Y,Kaminaga M.ANew CHF Correlation Scheme Proposed for Vertical Rectangular Channels Heated from Both Sides in Nuclear Research Reactors[J].Transaction of ASME,Journal of Heat Transfer,1993,6(4):115 ~426.
  • 8Kanminaga M.COOLOD-N:A Computer Code for the Analysis of Steady-state Thermal-hydraulics in Plate Type Research Reactor[J].JAERI-M,1990,90(21):2201 ~ 2213.
  • 9杨祖毛,王飞,王文康,程良成,彭兴建,黄彦平,廖建如,陈炳德,赵华.闭合回路单相自然循环稳态特性研究[J].核动力工程,1999,20(3):219-222. 被引量:13
  • 10杨祖毛,陈炳德,王飞黄,彦平,杨瑞昌.一维单相自然循环流量稳态解的型式及实验验证[J].核科学与工程,1999,19(3):248-253. 被引量:8

共引文献15

同被引文献12

引证文献1

二级引证文献1

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