Zobrazeno 1 - 10
of 10
pro vyhledávání: '"M. F. Dowling"'
Autor:
Said I. Abdel-Khalik, S. M. Ghiaasiaan, R. M. Stoddard, M. F. Dowling, Sheldon Jeter, A.M. Blasick
Publikováno v:
Experimental Thermal and Fluid Science. 26:1-14
The onset of flow instability (OFI) and critical heat flux (CHF) in heated thin horizontal annular flow passages cooled by subcooled water were investigated. For OFI, six different test sections, with inner diameter of 6.4 mm, annular gap widths of 0
Publikováno v:
International Journal of Heat and Mass Transfer. 44:2453-2459
Turbulent wall friction and forced convection heat transfer in a water-cooled trapezoidal channel were experimentally investigated. The parameter ranges were: Reynolds number=10 4 –8.6×10 4 , and Prandtl number=2.2–5.5. The channel hydraulic dia
Publikováno v:
International Journal of Heat and Mass Transfer. 42:4411-4415
Publikováno v:
Nuclear Science and Engineering. 133:106-117
Onset offlow instability (OFI) in uniformly heated microchannels cooled with subcooled water at very low flow rates was experimentally investigated. Four different microchannels, all of which were 22 cm long with a 16-cm-long heated section, were use
Autor:
Z. H. Quershi, S. M. Ghiaasiaan, J. E. Kennedy, M. F. Dowling, Said I. Abdel-Khalik, G. M. Roach, Sheldon Jeter
Publikováno v:
Journal of Heat Transfer. 122:118-125
Onset of nucleate boiling and onset of flow instability in uniformly heated microchannels with subcooled water flow were experimentally investigated using 22-cm long tubular test sections, 1.17 mm and 1.45 mm in diameter, with a 16-cm long heated len
Publikováno v:
Nuclear Science and Engineering. 131:411-425
Critical heat flux (CHF) associated with the flow of subcooled water in heated microchannels is experimentally investigated. Four different channels, all 16 cm in length, are used: two are circular...
Publikováno v:
Nuclear Technology. 111:80-91
Spent-fuel storage and disassembly basins at heavy water reactor facilities have maximum allowable temperature and tritium activity levels to protect personnel from exposure to radiation from the t...
Publikováno v:
Nuclear Science and Engineering. 115:185-192
Dilute aqueous solutions of two surface active agents (surfactants) were tested for their ability to suppress spontaneous steam explosions in molten tin/water systems. At 800C, 12 g of tin were dropped into aqueous solutions of a nonionic surfactant
Publikováno v:
Nuclear Science and Engineering. 113:300-313
The nuclear industry is a potential setting for steam explosion accidents; in this context, they are commonly referred to as fuel/coolant interactions (FCIs). Loss-of-coolant accidents that could lead to FCIs are considered to be unlikely. Neverthele
Publikováno v:
Heat Transfer: Volume 2.
The objectives of the work reported here were to experimentally study the critical heat flux in a heated thin, horizontal, annular flow passage cooled by subcooled water and to examine the applicability and relevance of the current predictive methods