A Critical Heat Generation for Safe Nuclear Fuels after a LOCA

This study applies a thermo-elasto-plastic-creep finite element procedure to the analysis of an accidental behavior of nuclear fuel as well as normal behavior. The result will be used as basic data for the robust design of nuclear power plant and fuels. We extended the range of mechanical strain fro...

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Bibliographic Details
Main Authors: Jae-Yong Kim, Dong-Bock Kim, Hee-Jeong Cho, Soon-Bum Kwon, Young-Doo Kwon
Format: Article
Language:English
Published: Wiley 2014-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2014/150985
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