Pool boiling CHF enhancement by graphene-oxide nanofluid under nuclear coolant chemical environments
Abstract
External reactor vessel cooling (ERVC) for in-vessel retention (IVR) of corium as a key severe accident management strategy can be achieved by flooding the reactor cavity during a severe accident. In this accident mitigation strategy, the decay heat removal capability depends on whether the imposed heat flux exceeds critical heat flux (CHF). To provide sufficient cooling for high-power reactors such as APR1400, there have been some R&D efforts...
Paper Details
Title
Pool boiling CHF enhancement by graphene-oxide nanofluid under nuclear coolant chemical environments
Published Date
Nov 1, 2012
Volume
252
Pages
184 - 191
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