Experimental Investigation on Flow-Induced Vibration of Fuel Rods in Supercritical Water Loop

The supercritical water-cooled reactor (SCWR) is one of the most promising Generation IV reactors. In order to make the fuel qualification test for SCWR, a research plan is proposed to test a small scale fuel assembly in a supercritical water loop. To ensure the structure safety of fuel assembly in...

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Bibliographic Details
Main Authors: Licun Wu, Daogang Lu, Yu Liu
Format: Article
Language:English
Published: Hindawi Limited 2014-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2014/769432