Effects of porous superhydrophilic surfaces on flow boiling critical heat flux in IVR accident scenarios

Critical Heat Flux (CHF) plays a key role in nuclear reactor safety both during normal operation as well as in accident scenarios. In particular,when an in-vessel retention (IVR) strategy is used as a severe accident management strategy, the reactor pressure vessel (RPV) cavity is flooded with water...

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Bibliographic Details
Main Authors: Atkhen, Kresna, Buongiorno, Jacopo, Azizian, Mohammad Reza, McKrell, Thomas J.
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Format: Article
Language:en_US
Published: American Nuclear Society ( ANS ) 2017
Online Access:http://hdl.handle.net/1721.1/108093
https://orcid.org/0000-0002-1827-1904