期刊文献+

重力注水下再淹没棒束通道数值模拟研究 被引量:1

Numerical Investigation on the Reflooding of a Hot Vertical Bundle-channel by Gravity
下载PDF
导出
摘要 基于棒束通道注水再淹没系统,提出重力注水方案,运用RELAP5/MOD3.2建立其再淹没模型,模拟从棒束底部依靠重力注水再淹没高温棒束通道时的骤冷现象。模拟结果显示:再淹没的过程中出现持续的流动振荡,冷却水周期性地注入、逐出,振荡过程可分为初始阶段的剧烈振荡和后续阶段的平稳振荡,在此期间的注入流量,棒束通道汽空间压力,壁面温度和传热系数都出现相应的周期性变化;同时进一步模拟分析了注入水入口尺寸、初始包壳温度、蒸汽出口尺寸三个因素对振荡的影响机制,发现其振荡周期和振荡幅度随注入口的增大,初始包壳温度的升高、蒸汽出口尺寸的减小而增大。 Based on the bundle reflooding system,gravity water injection project is proposed and reflooding phenomena with injecting water by gravity is investigated with RELAP5 code.The results showed that,there appear continued flow oscillation during the bottom reflooding,it can be divided into two stage,serious oscillation in the initial stage and relatively stable oscillation at later stage.And at the same time,flow rate,the pressure of steam in upper bundle channel,the temperature of heating rod as well as the coefficient of heat transfer show intermittent changes.Meanwhile,the influencing mechanism about water inlet size,the initial temperature of heating rod,steam outlet size is further studied upon this continuous oscillation,and it is found that the period and amplitude of this flow oscillation increase along with the increase of water inlet size,initial temperature of cladding,and the decrease of steam outlet size.
作者 杨生兴 陈金波 YANG Sheng-xing;CHEN Jin-bo(CNNC Key Laboratory on Nuclear Reactor Thermal-Hydraulics Technology,Chengdu,610041,China;School of Mechanical Engineering,SJTU,Shanghai,200240,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2018年第6期960-969,共10页 Nuclear Science and Engineering
基金 中国核动力院核反应堆系统设计技术重点实验室基金资助项目
关键词 重力注水 再淹没 流动振荡 Gravity water injection Reflooding Flow oscillation
  • 相关文献

参考文献2

二级参考文献22

  • 1Aritomi M, Horiguchi M, Sudi A. Thermal-Hydralics of Boiling Two-Phase Flow in High Conversion Light Water Reactors[J]. lnt. J. Multiphase Flow, 1992. 19(1): 51-63.
  • 2Saxena A K. Experimental Studies on Rewetting of Hot Vertical Annular Channel[J]. Nuclear Engineering and Design, 2001, 208:283-303.
  • 3Mishima.K, Boiling burnout at low flow rate and low pressure conditions[D]. Ph.D. Thesis Research Reactor Inst., Kyoto Univ., Japan., 1984.
  • 4Bestion D. lnterfacial Friction Determination for the ID-6 Equations Two Fluid Model Used in the CATHARE, Code[C]. European Two Phase Flow Group meeting, Southampton, 1985.
  • 5Griffith P. The Prediction of Low Quality Boiling Voids[J]. Transactions of the ASME, 1964. 86: 327-333.
  • 6Ishii M. One-Dimensional Drift-Flux Model and Constitutive Equations for Relative Motion Between Phases in Various Two-Phase Flow Regimes[R]. ANL-77-47, 1977.
  • 7Argonne National Laboratory. Chenetal N. Conceptual Design Loss-of-Coolant Accident Analysis for the Advanced Neutron Source Reactor[J]. Nuclear Technology, 1994, 11:105-114.
  • 8Tran T N, France D M. Small Circular and Rectangular Channel Boiling with Refrigerants[J]. Internantional Journal of Multiohase Flow. 1996. 22(3):485-498.
  • 9Hynek S J, Rhosenow W M, Bergles A B. Forced Convection Dispersed Flow Film Boiling[R]. MIT Heat Transfer Lab Report, DSR 70586-63, 1969.
  • 10Guo Yujun, Mishima K. A Non-Equilibrium Mechanistic Heat Transfer Model for Post-Dryout Dispersed Flow Regime[J]. Exp. Therm. Fluid Sci., 2002. 26:861-869.

共引文献3

同被引文献1

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