A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP
Depending on the specific event scenario and on the purpose of the analysis, the availability of calculation methods that are not implemented in the standard system thermal hydraulic codes might be required. This may imply the use of a dedicated fuel rod thermomechanical computer code. This paper p...
Main Authors: | , , , |
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Format: | Article |
Language: | English |
Published: |
Hindawi Limited
2011-01-01
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Series: | Science and Technology of Nuclear Installations |
Online Access: | http://dx.doi.org/10.1155/2011/929358 |