Saturated pool boiling from downward facing structured surfaces with grooves

被引：0
|
作者：
Zhong D. [1 ]
Meng J. [1 ]
Li Z. [1 ]
机构：
[1] Institutes of Engineering Thermal Physics, School of Aerospace Engineering, Tsinghua University, Beijing
来源：
Huagong Xuebao/CIESC Journal | 2016年 / 67卷 / 09期
关键词：
Bubble; Critical heat flux; Heat transfer; Orientation; Phase change; Surface;
D O I：
10.11949/j.issn.0438-1157.20160015
中图分类号：
学科分类号：
摘要：
In-vessel retention is a key severe accident management strategy now widely adopted by some nuclear power plants. The saturated pool boiling heat transfer coefficients and critical heat flux (CHF) were measured from downward facing structured surface with grooves in deionized water to enhance the CHF. The orientations were 5°, 30°, 45°, 60° and 90° (vertical). The results showed that the nucleate boiling heat transfer coefficients and the local CHF for structured surface with grooves were consistently higher than those for plain surface. Compared with plain surface, the CHF increase could reach 65%-90% for structured surface. The vapor blanket and wavy vapor layer bubble structures with different CHF trigger mechanisms on the downward facing surface at high heat fluxes were observed on structured surface. The enhancement of the local CHF and the nucleate boiling heat transfer coefficients was mainly due to the significantly increase of heat transfer area and the grooves that effectively improve surface wettability. © All Right Reserved.
引用
收藏
页码：3559 / 3565
页数：6
相关论文
共 20 条
  • [1] Henry R.E., Fauske H.K., External cooling of a reactor vessel under severe accident conditions, Nucl. Eng. Des., 139, 1, pp. 31-43, (1993)
  • [2] Rempe J.L., Suh K.Y., Cheung F.B., Et al., In-vessel retention-recent efforts and future needs, Proceedings of the Sixth International Topical Meeting on Nuclear Thermal Hydraulics, Operations and Safety, (2004)
  • [3] Rempe J.L., Suh K.Y., Cheung F.B., Et al., Insights from investigations of in-vessel retention for high powered reactors, Proceedings, 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, (2005)
  • [4] Rempe J.L., Suh K.Y., Cheung F.B., Et al., In-vessel Retention Strategy for High Power Reactors Final Report, (2005)
  • [5] Vishnev I.P., Effect of orienting the hot surface with respect to the gravitational field on the critical nucleate boiling of a liquid, Journal of Engineering Physics, 24, 1, pp. 43-48, (1973)
  • [6] El-Genk M.S., Guo Z., Transient boiling from inclined and downward-facing surfaces in a saturated pool, Int. J. Ref., 16, 6, pp. 414-422, (1993)
  • [7] Brusstar M.J., Merte J.H., Keller R.B., Et al., Effects of heater surface orientation on the critical heat flux (I): An experimental evaluation of models for subcooled pool boiling, Int. J. Heat Mass Trans., 40, 17, pp. 4007-4019, (1997)
  • [8] Kim J., Suh K., One-dimensional critical heat flux concerning surface orientation and gap size effects, Nucl. Eng. Des., 226, 3, pp. 277-292, (2003)
  • [9] Rouge S., SULTAN test facility for large-scale vessel coolability in natural convection at low pressure, Nucl. Eng. Des., 169, 1-3, pp. 185-195, (1997)
  • [10] Theofanous T.G., Syri S., The coolability limits of a reactor pressure vessel lower head, Nucl. Eng. Des., 169, 1, pp. 59-76, (1997)
12