Issue Section:
Technical Briefs
1.
Bowring, R. W., 1962, “Physical Model Based on Bubble Detachment and Calculation of Steam Voidage in the Subcooled Region of a Heated Channel,” OECD Halden Reactor Project Report HPR-10.
2.
Davis
E. J.
Anderson
G. H.
1966
, “The Incipience of Nucleate Boiling in Forced Convection Flow
,” AIChE Journal
, Vol. 12
, pp. 774
–780
.3.
Dougherty, T., Fighetti, C, McAssey, E., Reddy, G., Yang, B., Chen, K., and Qureshi, Z. C, 1989, “Flow Instability in Vertical Down-Flow at High Heat Fluxes,” ASME HTD-Vol. 199, pp. 17–23.
4.
Dougherty, T., Fighetti, C, Reddy, D., Yang, B., Jafri, T., McAssey, E., and Qureshi, Z., 1990, “Flow Boiling in Vertical Downflow,” Proceedings of the Ninth International Heat Transfer Conference, Vol. 2, Jerusalem, Israel.
5.
Dougherty, T. J., and Yang, B. W., 1995, “Flow Instability and Critical Heat Flux in a Natural Circulation Loop at Low Pressure,” Proceedings of the 1995 ASME National Heat Transfer Conference, ASME HTD-Vol. 316.
6.
Fleischer, A. S., McAssey, E. V., and Jones, G. F., 1997, “Influence of Bubble Formation on Pressure Drop in a Uniformly Heated Vertical Channel,” ASME Proceedings of the 32nd National Heat Transfer Conference, ASME HTD-Vol. 342.
7.
Levy
S.
1967
, “Forced Convective Subcooled Boiling-Prediction of Vapor Volumetric Fraction
,” International Journal of Heat and Mass Transfer
, Vol. 10
, pp. 951
–965
.8.
Martinelli
R. C.
Nelson
D. B.
1948
, “Prediction of Pressure Drop During Forced Circulation Boiling of Water
,” Transactions of the ASME
, Vol. 70
, p. 695
695
.9.
Saha, P., and Zuber, N., 1974, “Point of Net Vapor Generation and Vapor Void Fraction in Subcooled Boiling,” Proceedings of the 5th International Heat Transfer Conference, B4.7, Tokyo, Japan.
10.
Stelling
R.
McAssey
E. V.
Dougherty
T.
Yang
B.
1996
, “The Onset of Flow Instability for Downward Flow in Vertical Channels
,” ASME JOURNAL OF HEAT TRANSFER
, Vol. 118
, pp. 709
–714
.11.
Yang, B. W., Dougherty, T. J., Ouyang, W., McAssey, E. V., Smalec, L., 1993, “Flow Instability in Vertical Upflow Under Low Heat Flux Conditions,” Ninth Proceedings of Nuclear Thermal Hydraulics, American Nuclear Society Winter Annual Meeting, San Francisco, CA.
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