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自然循环蒸汽发生器倒U型管内流动不稳定性判别准则 被引量:1

Criteria of Flow Instabilities in Steam Generator U-Tubes with Natural Circulation
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摘要 针对自然循环蒸汽发生器倒U型管内流动不稳定的特点,利用无量纲分析方法建立管内流体控制方程.采用小扰动分析方法,得到倒U型管内流动不稳定的判别准则.通过对某型蒸汽发生器进行计算分析,获得判别准则随流体进口温度和弯管半径变化规律.计算结果表明:随着流体进口温度的升高,特征雷诺数增加,但是不同流体进口温度条件下特征雷诺数随弯管半径的变化规律不同.相对于流体进口温度,弯管半径对特征雷诺数的影响较小.所得结论为蒸汽发生器倒U型管内倒流管空间分布及倒流流量计算提供理论依据. For flow instabilities in inverted U-tubes steam generator (SG) , a dimensionless analysis is made for flow equation. Criteria of flow stabilities ( characteristic Reynolds number) are derived according to small perturbation analysis. With calculation for a certain type of SG, effect of inlet fluid temperature and U-tube bend radius on the criteria are studied. It shows that the characteristic Reynolds number increases with the increase of inlet fluid temperature. Relations between U-tube bend radius under different inlet temperatures are complex. It is useful for calculation of flows as well as space distribution of reverse flow in a SG.
出处 《计算物理》 CSCD 北大核心 2013年第4期515-519,共5页 Chinese Journal of Computational Physics
基金 海军工程大学博士研究生创新基金(HGBSJJ2012008)资助项目
关键词 蒸汽发生器 自然循环 流动不稳定性 判别准则 steam generator natural circulation flow instabilities criteria
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  • 1张勇,宋小明,黄伟.低流量下蒸汽发生器一次侧流量分配研究[J].核动力工程,2009,30(S1):56-59. 被引量:12
  • 2杨瑞昌,覃世伟,刘若雷.自然循环蒸汽发生器倒U型管内单相水流动及传热特性分析[J].工程热物理学报,2006,27(1):130-132. 被引量:11
  • 3王飞,卓文彬,肖泽军,陈炳德.立式倒U型管蒸汽发生器倒流现象及初步分析[J].原子能科学技术,2007,41(1):65-68. 被引量:19
  • 4Sanders J. Stability of Single-Phase Natural Circulation with Inverted U-Tube Steam Generators. Journal of Heat Transfer, 1988, 110:735-742.
  • 5Kukita Y, Nakamura H, Tasaka K, et al. Nonuniform Steam Generator U-Tube Flow Distribution During Natural Circulation Tests in ROSA-IV Large Scale Test Facility. Nuclear Science and Engineering, 1988, 99:289-298.
  • 6王飞,聂常华,黄彦平,等..自然循环静态特性研究,空泡物理和自然循环重点实验室年报..,,2003..130-135..
  • 7Jeong J J, Hwang M, Lee Y J, et al. Single-and TwoPhase Flow Characteristics in the Primary Side of a UTube Steam Generator. In: The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics. Seoul, Korea, 2003.
  • 8Stumpf H, Motly F, Schultz R, et al. Reverse Primary Side Flow in Steam Generators During Natural Circulation Cooling. American Society of Mechanical Engineering, Fluid Engineering Division(FED), 1987, 61:103-109.
  • 9Kukita Y, Nakamura H, Tasaka K, et al. Nonuniform Steam Generator U-Tube Flow Distribution during Natural Circulation Tests in ROSA-Ⅳ Large Scale Test Facility[J]. Nuclear Science and Engineering, 1988, 99: 289 - 298.
  • 10Schulz R R, Chapman J C, Kukita Y, et al. Single and Two-Phase Natural Circulation in Westinghouse Pressurized Water Reactor Simulators: Phenomena, Analysis and Scaling[C]. ASME FED, 1987, 61:59 - 70.

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