Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety substantiation

Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety substantiation

Numerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried out using the COREMELT code indicate the development and spreading of sodium boiling in the core accompanied with fluctuations of reactor technological parameters lasting over a period of several tens of a sec...

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Bibliographic Details
Main Authors: R.R. Khafizov, V.M. Poplavsky, V.I. Rachkov, A.P. Sorokin, Yu.M. Ashurko, A.V. Volkov, E.F. Ivanov, V.V. Privezentsev
Format: Article
Language:English
Published: National Research Nuclear University (MEPhI) 2015-10-01
Series:Nuclear Energy and Technology
Subjects:
Fact reactor
Sodium
Fuel subassembly mockup
Experimental studies
Boiling
Two-phase flow regime map
Heat transfer
Online Access:http://www.sciencedirect.com/science/article/pii/S2452303816000091

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http://www.sciencedirect.com/science/article/pii/S2452303816000091

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