Experimental investigation of the rewetting process at low steam pressures

Hinis, E.P.; Simopoulos, S.E.

dc.contributor.author	Hinis, E.P.
dc.contributor.author	Simopoulos, S.E.
dc.date.accessioned	2021-04-29T11:32:11Z
dc.date.available	2021-04-29T11:32:11Z
dc.identifier.other	ISBN 86-7306-012-5	el
dc.identifier.uri	https://dspace.lib.ntua.gr/xmlui/handle/123456789/53377
dc.identifier.uri	http://dx.doi.org/10.26240/heal.ntua.21075
dc.language.iso	en	en
dc.rights	Αναφορά Δημιουργού-Μη Εμπορική Χρήση-Όχι Παράγωγα Έργα 3.0 Ελλάδα	*
dc.rights.uri	http://creativecommons.org/licenses/by-nc-nd/3.0/gr/	*
dc.subject	Πυρηνική Τεχνολογία	el
dc.subject	Πυρηνικοί αντιδραστήρες	el
dc.subject	Ράβδοι πυρηνικού καυσίμου	el
dc.subject	Επανάψυξη	el
dc.subject	Υγρό μέτωπο	el
dc.subject	Nuclear Engineering	en
dc.subject	Nuclear reactors	en
dc.subject	Nuclear fuel rods	en
dc.subject	Rewetting	en
dc.subject	Quench front	en
dc.title	Experimental investigation of the rewetting process at low steam pressures	en
heal.type	conferenceItem
heal.classification	Nuclear Engineering	el
heal.language	en
heal.access	free
heal.recordProvider	ntua	el
heal.publicationDate	1996-10-06
heal.bibliographicCitation	Hinis E.P. and Simopoulos S.E., (1996), “Experimental investigation of the rewetting process at low steam pressures”, Proceedings of the Yugoslav Nuclear Society Conference, YUNSC '96, October 6-9, 1996, Belgrade, Yugoslavia	en
heal.abstract	The rewetting of the overheated water cooled nuclear reactor fuel rods after a Loss-of-Coolant-Accident, which is defined as the re-establishment of a water film on the hot rod surfaces, is an important process for the safety of nuclear reactors. Several water experiments have been carried out to investigate the rewetting phenomena and to predict the liquid film behaviour either at atmospheric conditions or in a steam environment. Yet, there seems to be a scarcity of experimental data for the very important low pressure range from 2 to 7 bar with parameters the liquid film flowrate and the subcooling. An experimental facility to simulate two-phase low-pressure water flow phenomena has been designed, constructed and employed to investigate the rewetting process of hot surfaces in a water-steam environment at pressures in the above range, as well as at atmospheric conditions; the facility is on-line interfaced to computers which control its operation and undertake all the data acquisition tasks. The present paper describes the experimental work aimed at studying the wet front propagation along a stainless steel fuel rod in a top-flooding saturated water-steam environment in the pressure range 1 - 7 bar, under various initial wall temperatures up to 550 °C and at a liquid flowrate of 1imin-1. Following the experimental results a correlation has been derived to predict the rewetting rate as a function of pressure and initial wall temperaturi. This correlation agrees well with formerly proposed correlations at higher pressures, thus permitting to extend their validity down to the pressure of 1 bar. Furthermore, a numerical method is introduced to experimentally evaluate the wet front position along the rod.	en
heal.publisher	Printing House of the VINCA Institute of Nuclear Sciences	en
heal.fullTextAvailability	false
heal.conferenceName	Yugoslav Nuclear Society Conference (YUNSC '96)	en
heal.conferenceItemType	full paper