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Assessment of the analysis capability for core-wide PWR pellet-clad interaction screening of Watts Bar Unit 1...

by Nathan Capps, Shane G Stimpson, Kevin T Clarno, Brian Wirth, Y.r. (joe) Rashid
Publication Type
Journal
Journal Name
Nuclear Engineering and Design
Publication Date
Page Numbers
131 to 144
Volume
333

This report illustrates the application of the Virtual Environment for Reactor Applications simulation environment to pressurized water reactor core-wide pellet-clad interaction screening, with emphasis on the multi-dimensional analysis capabilities of the BISON fuel performance code. The Virtual Environment for Reactor Applications codes utilized in this effort include the BISON fuel performance code and the VERA-CS sub-element, which combines the MPACT neutron transport code and the COBRA-TF thermal-hydraulics code. The target reactor for this work is Watts Bar Unit 1, cycle 6 and cycle 7, selected on the basis that pellet-clad interaction failures had occurred during power start up in both cycles, despite the moderate power levels. These instances of failure at Watts Bar Unit 1 offered an interesting test of the code’s veracity and a particularly challenging condition for this assessment.